Laboratory Scoping Tests Of Decontamination Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, Kathryn M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, Charles A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, Charles L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Wilmarth, William R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-01-21

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task seeks to examine the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also

Test for Jet Flow Induced by Steam Jet Condensation Using the GIRLS Facility

International Nuclear Information System (INIS)

Kim, Yeon Sik; Yoon, Y. J.; Song, C. H.

2007-03-01

To investigate the characteristics of the turbulent jet induced by steam jet condensation in a water tank through a single-hole sparger an experimental investigation was performed using the GIRLS facility. The experiments were conducted with respect to two cases, e.g. horizontal and vertical upward injections. For the measurements, pitot tube and thermocouples were used for turbulent flow velocity and temperatures, respectively. Overall flow shapes of the turbulent jet by the steam jet condensation are similar to those of axially symmetric turbulent jet flows. The angular coefficients of turbulent rays are quantitatively comparable between the traditional turbulent jet flows and the turbulent jet flows induced by the steam jet condensation in this work. Although the turbulent flows were induced by the horizontally injected steam jet condensation, general theory of turbulent jets was found to be applicable to the turbulent flows of this work. But for the vertically upward injection case, experimental data were quite deviated from the theoretical ones, which is considered due to the buoyancy effect

Waste Treatment And Immobilization Plant U. S. Department Of Energy Office Of River Protection Submerged Bed Scrubber Condensate Disposition Project - Abstract no. 13460

International Nuclear Information System (INIS)

Yanochko, Ronald M; Corcoran, Connie

2012-01-01

The Hanford Waste Treatment and Immobilization Plant (WTP) will generate an off-gas treatment system secondary liquid waste stream [submerged bed scrubber (SBS) condensate], which is currently planned for recycle back to the WTP Low Activity Waste (LAW) melter. This SBS condensate waste stream is high in Tc-99, which is not efficiently captured in the vitrified glass matrix. A pre-conceptual engineering study was prepared in fiscal year 2012 to evaluate alternate flow paths for melter off-gas secondary liquid waste generated by the WTP LAW facility. This study evaluated alternatives for direct off-site disposal of this SBS without pre-treatment, which mitigates potential issues associated with recycling

Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

Energy Technology Data Exchange (ETDEWEB)

Adamson, Duane J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, Charles A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, Charles L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Wilmarth, William R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-01-01

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter

Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

International Nuclear Information System (INIS)

Adamson, Duane J.; Nash, Charles A.; McCabe, Daniel J.; Crawford, Charles L.; Wilmarth, William R.

2014-01-01

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter

Performance Evaluation of the International Space Station Flow Boiling and Condensation Experiment (FBCE) Test Facility

Science.gov (United States)

Hasan, Mohammad; Balasubramaniam, R.; Nahra, Henry; Mackey, Jeff; Hall, Nancy; Frankenfield, Bruce; Harpster, George; May, Rochelle; Mudawar, Issam; Kharangate, Chirag R.;

Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

International Nuclear Information System (INIS)

Blinkov, V.N.; Melikhov, O.I.; Melikhov, V.I.; Davydov, M.V.; Wolff, H.; Arndt, S.

2012-01-01

In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3). Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.

Engineering work plan for implementing the Process Condensate Recycle Project at the 242-A evaporator

International Nuclear Information System (INIS)

Haring, D.S.

1995-01-01

The 242-A Evaporator facility is used to reduce the volume of waste stored in the Hanford double shell tanks. This facility uses filtered raw water for cooling, de-entrainment pad sprays, pump seal water, and chemical tank make-up. Some of these uses result in the introduction of filtered raw water into the process, thus increasing the volume of waste requiring evaporation and subsequent treatment by the 200 East Effluent Treatment Facility. The pump seal water and the de-entrainment pad spray systems were identified as candidates for a waste minimization upgrade. This work plan describes the activities associated with the design, installation, testing and initial operation of the process condensate recycle system. Implementation of the process condensate recycle system will permit the use of process condensate in place of raw water for the de-entrainment pad sprays and pump seals. This will reduce the amount of low-level liquid waste and generated during facility operation through source reduction and recycling

Investigation of variable compositions on the removal of technetium from Hanford Waste Treatment Plant low activity waste melter off-gas condensate simulant

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, Kathryn M. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pareizs, John M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-03-29

The Low Activity Waste (LAW) vitrification facility at the Hanford Waste Treatment and Immobilization Plant (WTP) will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the offgas system. The plan for disposition of this stream during baseline operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. The primary reason to recycle this stream is so that the semi-volatile ⁹⁹Tc isotope eventually becomes incorporated into the glass. This stream also contains non-radioactive salt components that are problematic in the melter, so diversion of this stream to another process would eliminate recycling of these salts and would enable simplified operation of the LAW melter and the Pretreatment Facilities. This diversion from recycling this stream within WTP would have the effect of decreasing the LAW vitrification mission duration and quantity of glass waste. The concept being tested here involves removing the ⁹⁹Tc so that the decontaminated aqueous stream, with the problematic salts, can be disposed elsewhere.

Preparation and evaporation of Hanford Waste treatment plant direct feed low activity waste effluent management facility simulant

Energy Technology Data Exchange (ETDEWEB)

Adamson, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Howe, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-09-07

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate, LMOGC) from the off-gas system. The baseline plan for disposition of this stream during full WTP operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation, and recycled to the LAW vitrification facility. However, during the Direct Feed LAW (DFLAW) scenario, planned disposition of this stream involves concentrating the condensate in a new evaporator at the Effluent Management Facility (EMF) and returning it to the LAW melter. The LMOGC stream will contain components, e.g. halides and sulfates, that are volatile at melter temperatures, have limited solubility in glass waste forms, and present a material corrosion concern. Because this stream will recycle within WTP, these components are expected to accumulate in the LMOGC stream, exacerbating their impact on the number of LAW glass containers that must be produced. Diverting the stream reduces the halides and sulfates in the glass and is a key objective of this program. In order to determine the disposition path, it is key to experimentally determine the fate of contaminants. To do this, testing is needed to account for the buffering chemistry of the components, determine the achievable evaporation end point, identify insoluble solids that form, determine the formation and distribution of key regulatoryimpacting constituents, and generate an aqueous stream that can be used in testing of the subsequent immobilization step. This overall program examines the potential treatment and immobilization of the LMOGC stream to enable alternative disposal. The objective of this task was to (1) prepare a simulant of the LAW Melter Off-gas Condensate expected during DFLAW operations, (2) demonstrate evaporation in order to predict the final composition of the effluents from the EMF

Steam condensation induced water hammer in a vertical up-fill configuration within an integral test facility. Experiments and computational simulations

Energy Technology Data Exchange (ETDEWEB)

Dirndorfer, Stefan

2017-01-17

Condensation induced water hammer is a source of danger and unpredictable loads in pipe systems. Studies concerning condensation induced water hammer were predominantly made for horizontal pipes, studies concerning vertical pipe geometries are quite rare. This work presents a new integral test facility and an analysis of condensation induced water hammer in a vertical up-fill configuration. Thanks to the state of the art technology, the phenomenology of vertical condensation induced water hammer can be analysed by means of sufficient high-sampled experimental data. The system code ATHLET is used to simulate UniBw condensation induced water hammer experiments. A newly developed and implemented direct contact condensation model enables ATHLET to calculate condensation induced water hammer. Selected experiments are validated by the modified ATHLET system code. A sensitivity analysis in ATHLET, together with the experimental data, allows to assess the performance of ATHLET to compute condensation induced water hammer in a vertical up-fill configuration.

Steam condensation induced water hammer in a vertical up-fill configuration within an integral test facility. Experiments and computational simulations

International Nuclear Information System (INIS)

Dirndorfer, Stefan

2017-01-01

Condensation induced water hammer is a source of danger and unpredictable loads in pipe systems. Studies concerning condensation induced water hammer were predominantly made for horizontal pipes, studies concerning vertical pipe geometries are quite rare. This work presents a new integral test facility and an analysis of condensation induced water hammer in a vertical up-fill configuration. Thanks to the state of the art technology, the phenomenology of vertical condensation induced water hammer can be analysed by means of sufficient high-sampled experimental data. The system code ATHLET is used to simulate UniBw condensation induced water hammer experiments. A newly developed and implemented direct contact condensation model enables ATHLET to calculate condensation induced water hammer. Selected experiments are validated by the modified ATHLET system code. A sensitivity analysis in ATHLET, together with the experimental data, allows to assess the performance of ATHLET to compute condensation induced water hammer in a vertical up-fill configuration.

A Facile, Choline Chloride/Urea Catalyzed Solid Phase Synthesis of Coumarins via Knoevenagel Condensation

Directory of Open Access Journals (Sweden)

Hosanagara N. Harishkumar

2011-01-01

Full Text Available The influence of choline chloride/urea ionic liquid in solid phase on the Knoevenagel condensation is demonstrated. The active methylene compounds such as meldrum’s acid, diethylmalonate, ethyl cyanoacetate, dimethylmalonate, were efficiently condensed with various salicylaldehydes in presence of choline chloride/urea ionic liquid without using any solvents or additional catalyst. The reaction is remarkably facile because of the air and water stability of the catalyst, and needs no special precautions. The reactions were completed within 1hr with excellent yields (95%. The products formed were sufficiently pure, and can be easily recovered. The use of ionic liquid choline chloride/urea in solid phase offered several significant advantages such as low cost, greater selectivity and easy isolation of products.

LABORATORY OPTIMIZATION TESTS OF TECHNETIUM DECONTAMINATION OF HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE OFF-GAS CONDENSATE SIMULANT

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, K.; Nash, C.; McCabe, D.

2014-09-29

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also

Evaporation Of Hanford Waste Treatment Plant Direct Feed Low Activity Waste Effluent Management Facility Core Simulant

Energy Technology Data Exchange (ETDEWEB)

Adamson, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Mcclane, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-09-01

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate, LMOGC) from the off-gas system. The baseline plan for disposition of this stream during full WTP operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation, and recycled to the LAW vitrification facility. However, during the Direct Feed LAW (DFLAW) scenario, planned disposition of this stream is to evaporate it in a new evaporator, in the Effluent Management Facility (EMF), and then return it to the LAW melter. It is important to understand the composition of the effluents from the melter and new evaporator, so that the disposition of these streams can be accurately planned and accommodated. Furthermore, alternate disposition of the LMOGC stream would eliminate recycling of problematic components, and would reduce the need for closely integrated operation of the LAW melter and the Pretreatment Facilities. Long-term implementation of this option after WTP start-up would decrease the LAW vitrification mission duration and quantity of glass waste, amongst the other operational complexities such a recycle stream presents. In order to accurately plan for the disposition path, it is key to experimentally determine the fate of contaminants. To do this, testing is needed to accurately account for the buffering chemistry of the components, determine the achievable evaporation end point, identify insoluble solids that form, and determine the distribution of key regulatory-impacting constituents. The LAW Melter Off-Gas Condensate stream will contain components that are volatile at melter temperatures, have limited solubility in the glass waste form, and represent a materials corrosion concern, such as halides and sulfate. Because this stream will recycle within WTP, these components will accumulate in the Melter Condensate

Neutron research on condensed matter: a study of the facilities and scientific opportunities in the United States

International Nuclear Information System (INIS)

1977-01-01

An in-depth review of the present status and future potential of the applications of low-energy neutron scattering to research in the condensed-matter sciences, including physics, chemistry, biology, and metallurgy is presented. The study shows that neutron scattering technology has proven to be of enormous importance to research in the above areas and especially to those of solid-state physics and chemistry. The main emphasis is on the scattering of low-energy neutrons by condensed matter. Since the same type of neutron source facilities can be used for the study of radiation damage, this related topic has also been included

Comparison of condensation correlations in CATHARE for modelling isolation condenser experiment

International Nuclear Information System (INIS)

Sorjonen, J.; Kalli, H.

1996-01-01

CATHARE is a thermal-hydraulic computer code developed at the Centre d'Etudes Nucleaires de Grenoble (CENG) for nuclear power plant safety analysis. Behaviour of a new Cathare condensation correlation have been studied. The code has been applied to Isolation Condenser (IC) experiment conducted in PIPER-ONE facility. PIPER-ONE simulates a General Electric BWR-6 with volume and height scaling ratios 1/2200 and 1/1, respectively. The facility is installed at Dipartimento di Costruzioni Meccaniche e Nucleari of Pisa University. The facility was equipped with an once-through heat exchanger immersed in a pool of ambient temperature water, installed roughly 10 m above the core, in the aim to reproduce qualitatively the phenomenologies expected for Isolation Condenser in the Simplified BWR (SBWR). Experiment PO-IC-02 included two subsequent power levels with initial pressure of 5.1 MPa. The IC was active during the whole experiment except in the time period between the two different power levels. A previous calculation of above mentioned experiment by Cathare2 V1.3E showed some lacks in the condensation correlation of the code. A new correlation has been developed in Centre d'Etudes Nucleaires de Grenoble (CENG). The new calculation of the PO-IC-02 experiment by Cathare2 Vl.3U 1 with the new correlation gave results consistent with the experiment in the condensing zone of the IC. Also the overall pressure trend was reproduced with estimated heat losses to the environment. A comparison with previously obtained Relap5/Mod3. 1 results is also shown in the present document. (author) (18 refs.)

State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

International Nuclear Information System (INIS)

1993-08-01

Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS

Effects of non-condensable gas on the condensation of steam

International Nuclear Information System (INIS)

Jackson, J.D.; An, P.; Reinert, A.; Ahmadinejad, M.

2000-01-01

The experimental work reported here was undertaken with the aim of extending the database currently available on the condensation of steam in the presence of non-condensable gases and thereby improving the empirical input to thermal-hydraulic codes which might be used for design and safety assessment of advanced water-cooled nuclear reactors. Heat was removed from flowing mixtures of steam and air in a test section by means of a water-cooled condensing plate. The test facility constructed for the study incorporates a degassing unit which supplies water to a boiler. This delivers steam steadily to a mixing chamber where it joins with a flow of preheated air. The mixture of steam and air is supplied to the bottom of a cylindrical test section in which it flows upwards over a double sided condensing plate which can be vertical, inclined or horizontal, The rate at which heat is removed by cooling water flowing through internal passages in the plate can de determined calorimetrically knowing the flow rate of the water and its temperature rise. After commissioning experiments had shown that reliable measurements of condensation heat transfer rate could be made using the test facility, a programme of development work followed in the course of which three different designs of condensing plate were evaluated in turn. The version eventually used in the main programme of experiments which followed was made from copper. However, its surfaces were coated with a thin layer of nickel and then with one of chromium. It was found that such a surface consistently promoted dropwise condensation and showed no signs of deterioration after lengthy periods of use. The rate of heat removal from pure steam and from mixtures of steam and air in varying proportions was measured as a function of plate sub-cooling for a variety of plate orientations. (author)

Wastewater Treatment Facilities

Data.gov (United States)

Iowa State University GIS Support and Research Facility — Individual permits for municipal, industrial, and semi-public wastewater treatment facilities in Iowa for the National Pollutant Discharge Elimination System (NPDES)...

Outcome of endodontic treatment of teeth filled using lateral condensation versus vertical compaction (Schilder's technique).

Science.gov (United States)

Aqrabawi, Jamal A

2006-02-15

The purpose of this prospective clinical and radiographic investigation was to assess the treatment results following endodontic therapy of teeth filled with lateral condensation versus teeth filled with vertical compaction of warm gutta-percha. A total of 290 patients were treated using the standardized step-back technique for canal preparation, which were filled with either lateral condensation or vertical compaction in one single session. Five years later, the treatment results were assessed clinically and radiographically and related to the type of the obturation technique using Chi-square analysis. Of the 340 teeth that were reexamined, 160 teeth were filled with lateral condensation, and 180 teeth were filled with vertical condensation. The results showed a significantly higher success rate for the vertical compaction versus the lateral condensation technique of teeth presented with preoperative periapical lesions P<0.04. Regardless of the preoperative periapical status of the teeth, no statistically significant difference was found between the two techniques. The overall success rate of both filling techniques was 80.3%.

Vapor condensation device

International Nuclear Information System (INIS)

Sakurai, Manabu; Hirayama, Fumio; Kurosawa, Setsumi; Yoshikawa, Jun; Hosaka, Seiichi.

1992-01-01

The present invention enables to separate and remove 14 C as CO 3 - ions without condensation in a vapor condensation can of a nuclear facility. That is, the vapor condensation device of the nuclear facility comprises (1) a spray pipe for spraying an acidic aqueous solution to the evaporation surface of an evaporation section, (2) a spray pump for sending the acidic aqueous solution to the spray pipe, (3) a tank for storing the acidic aqueous solution, (4) a pH sensor for detecting pH of the evaporation section, (5) a pH control section for controlling the spray pump, depending on the result of the detection of the pH sensor. With such a constitution, the pH of liquid wastes on the vaporization surface is controlled to 7 by spraying an aqueous solution of dilute sulfuric acid to the evaporation surface, thereby enabling to increase the transfer rate of 14 C to condensates to 60 to 70%. If 14 C is separated and removed as a CO 2 gas from the evaporation surface, the pH of the liquid wastes returns to the alkaline range of 9 to 10 and the liquid wastes are returned to a heating section. The amount of spraying the aqueous solution of dilute sulfuric acid can be controlled till the pH is reduced to 5. (I.S.)

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

International Nuclear Information System (INIS)

1993-08-01

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

Integral Reactor Containment Condensation Model and Experimental Validation

Energy Technology Data Exchange (ETDEWEB)

Wu, Qiao [Oregon State Univ., Corvallis, OR (United States); Corradini, Michael [Univ. of Wisconsin, Madison, WI (United States)

2016-05-02

This NEUP funded project, NEUP 12-3630, is for experimental, numerical and analytical studies on high-pressure steam condensation phenomena in a steel containment vessel connected to a water cooling tank, carried out at Oregon State University (OrSU) and the University of Wisconsin at Madison (UW-Madison). In the three years of investigation duration, following the original proposal, the planned tasks have been completed: (1) Performed a scaling study for the full pressure test facility applicable to the reference design for the condensation heat transfer process during design basis accidents (DBAs), modified the existing test facility to route the steady-state secondary steam flow into the high pressure containment for controllable condensation tests, and extended the operations at negative gage pressure conditions (OrSU). (2) Conducted a series of DBA and quasi-steady experiments using the full pressure test facility to provide a reliable high pressure condensation database (OrSU). (3) Analyzed experimental data and evaluated condensation model for the experimental conditions, and predicted the prototypic containment performance under accidental conditions (UW-Madison). A film flow model was developed for the scaling analysis, and the results suggest that the 1/3 scaled test facility covers large portion of laminar film flow, leading to a lower average heat transfer coefficient comparing to the prototypic value. Although it is conservative in reactor safety analysis, the significant reduction of heat transfer coefficient (50%) could under estimate the prototypic condensation heat transfer rate, resulting in inaccurate prediction of the decay heat removal capability. Further investigation is thus needed to quantify the scaling distortion for safety analysis code validation. Experimental investigations were performed in the existing MASLWR test facility at OrST with minor modifications. A total of 13 containment condensation tests were conducted for pressure

Full scaled tests of the KERENA trademark containment cooling condenser at the INKA test facility

International Nuclear Information System (INIS)

Leyer, Stephan; Maisberger, Fabian; Lineva, Natalia; Wagner, Thomas; Doll, Mathias; Herbst, Vasilli; Wich, Michael

2010-01-01

KERENA trademark is a medium-capacity boiling water reactor. It combines passive safety systems with active safety equipment of service-proven design. The passive systems utilize basic laws of physics, such as gravity and natural convection, enabling them to function without any power supply or actuation by instrumentation and control (I and C) equipment. They are designed to bring the plant to a safe and stable condition without the aid of active systems. Furthermore, the passive safety features partially replace the active systems, which reduces costs significantly and provides a safe, reliable and economically competitive plant design. At the new test facility at Karlstein called INKA (Integral Test Stand Karlstein), the key components of the KERENA trademark passive safety concept - the Emergency Condenser (EC), the Containment Cooling Condenser (CCC) and the passive core flooding system (PCFS) - are presently under full-scale testing,. Integral system tests will also be performed to show how the passive safety systems interact under various anticipated accident conditions and to demonstrate the ability of the passive systems to bring the plant to a safe and stable condition without the aid of active systems or actuation by I and C signals. The passive pressure pulse transmitter (PPPT) will be included in these integral tests. In this report the experimental setup and the first test results with the full scaled Containment Cooling Condenser will be described. (orig.)

Physics through the 1990s: condensed-matter physics

International Nuclear Information System (INIS)

1986-01-01

The volume presents the current status of condensed-matter physics from developments since the 1970s to opportunities in the 1990s. Topics include electronic structure, vibrational properties, critical phenomena and phase transitions, magnetism, semiconductors, defects and diffusion, surfaces and interfaces, low-temperature physics, liquid-state physics, polymers, nonlinear dynamics, instabilities, and chaos. Appendices cover the connections between condensed-matter physics and applications of national interest, new experimental techniques and materials, laser spectroscopy, and national facilities for condensed-matter physics research. The needs of the research community regarding support for individual researchers and for national facilities are presented, as are recommendations for improved government-academic-industrial relations

Clinical analysis of heat gutta-percha vertical condensation in the treatment of pulpitis and periapical periodontitis

Directory of Open Access Journals (Sweden)

Li Fan

2016-07-01

Full Text Available Objective: To explore the clinical effect of heat gutta-percha vertical condensation in the treatment of pulpitis and periapical periodontitis. Methods: A total of 120 patients with pulpitis and periapical periodontitis who were admitted in our hospital from February, 2015 to February, 2016 were included in the study and randomized into the observation group and the control group. The patients in the observation group were given heat gutta-percha vertical condensation for root canal filling, while the patients in the control group were given cold gutta-percha lateral condensation root canal filling. The root canal filling was evaluated. The changes of GI, SBI, and PD before and after treatment were observed. Results: The correct filling, shorting filling, and extra filling in the observation group were significantly superior to those in the control group. After treatment, GI, SBI, and PD were significantly reduced, and the reduced degree in the observation group was significantly superior to that in the control group. Conclusions: Heat gutta-percha vertical condensation in the treatment of pulpitis and periapical periodontitis can significantly enhance the therapeutic effect, and improve GI, SBI, and PD, with a significant clinical effect; therefore, it deserves to be widely recommended.

Electrical/instrumentation acceptance test report for Project C-018H, 242-A Evaporator/PUREX Plant condensate treatment facility

International Nuclear Information System (INIS)

Compau, R.A. Jr.

1995-01-01

This project is part of the 200 Area Effluent Treatment Facility. The acceptance test procedure describes test methods for leak detection units, pump flow switches, pump level control valves, room air temperature monitor, leachate pump status contacts, basin pump status contacts, catch basin leak detector, leachate level monitors, and basin level monitors. These are all components of the C-018H Collection System

Implementation and validation of the condensation model for containment hydrogen distribution studies

International Nuclear Information System (INIS)

Ravva, Srinivasa Rao; Iyer, Kannan N.; Gupta, S.K.; Gaikwad, Avinash J.

2014-01-01

Highlights: • A condensation model based on diffusion was implemented in FLUENT. • Validation of a condensation model for the H 2 distribution studies was performed. • Multi-component diffusion is used in the present work. • Appropriate grid and turbulence model were identified. - Abstract: This paper aims at the implementation details of a condensation model in the CFD code FLUENT and its validation so that it can be used in performing the containment hydrogen distribution studies. In such studies, computational fluid dynamics simulations are necessary for obtaining accurate predictions. While steam condensation plays an important role, commercial CFD codes such as FLUENT do not have an in-built condensation model. Therefore, a condensation model was developed and implemented in the FLUENT code through user defined functions (UDFs) for the sink terms in the mass, momentum, energy and species balance equations together with associated turbulence quantities viz., kinetic energy and dissipation rate. The implemented model was validated against the ISP-47 test of TOSQAN facility using the standard wall functions and enhanced wall treatment approaches. The best suitable grid size and the turbulence model for the low density gas (He) distribution studies are brought out in this paper

Investigation of bubble-condenser operation under large break LOCA conditions

International Nuclear Information System (INIS)

Blinkov, V.; Melikhov, O.; Melikhov, V.; Davydov, M.; Sokolin, A.; Hoffmann, D.; Simon, U.; Bajsz, J.

2000-01-01

In the framework of the PHARE/TACIS project, the experimental test facility for bubble condenser experimental qualification was built at Electrogorsk Research and Engineering Centre. The test facility contains high pressure system, compartments upstream of the bubble condenser and a section of the bubble condenser system. The scaling of the test facility is 1:100. The high pressure system consists of five vessels to appropriately model the leak functions (mass flow rate and enthalpy) during the loss of coolant accidents postulated in the design of VVER-440/V213. Design basis accident (LB LOCA) was experimentally and analytically considered. Results of pre-test analysis with ATHLET and DRASYS codes for determination of necessary test parameters and post-test analysis of three tests are presented. (author)

Code-experiment comparison on wall condensation tests in the presence of non-condensable gases-Numerical calculations for containment studies

Energy Technology Data Exchange (ETDEWEB)

Malet, J., E-mail: jeanne.malet@irsn.fr [Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES, SCA, BP 68, 91192 Gif-sur-Yvette (France); Porcheron, E.; Dumay, F.; Vendel, J. [Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES, SCA, BP 68, 91192 Gif-sur-Yvette (France)

2012-12-15

Highlights: Black-Right-Pointing-Pointer Steam condensation on walls has been investigated in the TOSQAN vessel. Black-Right-Pointing-Pointer Experiments on 7 different tests have been performed. Black-Right-Pointing-Pointer Different steam injections and wall temperatures are used. Black-Right-Pointing-Pointer Simulations are performed in 2D using the TONUS code. Black-Right-Pointing-Pointer Code-experiments comparisons at many different locations show a good agreement. - Abstract: During the course of a severe Pressurized Water Reactor accident, pressurization of the containment occurs and hydrogen can be produced by the reactor core oxidation and distributed in the containment according to convection flows and wall condensation. Filmwise wall condensation in the presence of non-condensable gases is a subject of many interests and extensive studies have been performed in the past. Some empirical correlations have demonstrated their limit for extrapolation under different thermal-hydraulic conditions and at different geometries/scales. The French Institute for Radiological Protection and Nuclear Safety (IRSN) has developed a numerical tool and an experimental facility in order to investigate free convection flows in the presence of condensation. The objective of this paper is to present numerical results obtained on different wall condensation tests in 7 m{sup 3} volume vessel (TOSQAN facility), and to compare them with the experimental ones. Over eight tests are considered here, and code-experiment comparison is performed on many different locations, giving an extensive insight of the code assessment for air-steam mixture flows involving wall condensation in the presence of non-condensable gases.

Condensate from a two-stage gasifier

DEFF Research Database (Denmark)

Bentzen, Jens Dall; Henriksen, Ulrik Birk; Hindsgaul, Claus

2000-01-01

Condensate, produced when gas from downdraft biomass gasifier is cooled, contains organic compounds that inhibit nitrifiers. Treatment with activated carbon removes most of the organics and makes the condensate far less inhibitory. The condensate from an optimised two-stage gasifier is so clean...... that the organic compounds and the inhibition effect are very low even before treatment with activated carbon. The moderate inhibition effect relates to a high content of ammonia in the condensate. The nitrifiers become tolerant to the condensate after a few weeks of exposure. The level of organic compounds...... and the level of inhibition are so low that condensate from the optimised two-stage gasifier can be led to the public sewer....

Status of the full scale component testing of the KERENA TM emergency condenser and Containment Cooling Condenser

International Nuclear Information System (INIS)

Leyer, S.; Maisberger, F.; Herbst, V.; Doll, M.; Wich, M.; Wagner, T.

2010-01-01

KERENA TM (SWR1000) is an innovative boiling water reactor concept with passive safety systems. In order to verify the functionality of the passive components required for the transient and accident management, the test facility INKA (Integral-Versuchstand Karlstein) is build in Karlstein (Germany). The key elements of the KERENA TM passive safety concept -the Emergency Condenser, the Containment Cooling Condenser, the Passive Core Flooding System and the Passive Pressure Pulse Transmitter - will be tested at INKA. The Emergency Condenser system transfers heat from the reactor pressure vessel to the core flooding pools of the containment. The heat introduced into the containment during accidents will be transferred to the main heat sink for passive accident management (Shielding/Storage Pool) via the Containment Cooling Condensers. Therefore both systems are part of the passive cooling chain connecting the heat source RPV (Reactor Pressure Vessel) with the heat sink. At the INKA test facility both condensers are tested in full scale setup, in order to determine the heat transfer capacity as function of the main input parameters. For the EC these are the RPV pressure, the RPV water level, the containment pressure and the water temperature of the flooding pools. For the Containment Cooling Condenser the heat transfer capacity is a function of the containment pressure, the water temperature of the Shielding/Storage Pool and the fraction of non -condensable gases in the containment. The status of the test program and the available test data will be presented. An outlook of the future test of the passive core flooding system and the integral system test including also the passive pressure pulse transmitter will be given. (authors)

Liquid Effluent Retention Facility/Effluent Treatment Facility Hazards Assessment

International Nuclear Information System (INIS)

Simiele, G.A.

1994-01-01

This document establishes the technical basis in support of Emergency Planning activities for the Liquid Effluent Retention Facility and Effluent Treatment Facility the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

Maintaining steam/condensate lines

International Nuclear Information System (INIS)

Russum, S.A.

1992-01-01

Steam and condensate systems must be maintained with the same diligence as the boiler itself. Unfortunately, they often are not. The water treatment program, critical to keeping the boiler at peak efficiency and optimizing operating life, should not stop with the boiler. The program must encompass the steam and condensate system as well. A properly maintained condensate system maximizes condensate recovery, which is a cost-free energy source. The fuel needed to turn the boiler feedwater into steam has already been provided. Returning the condensate allows a significant portion of that fuel cost to be recouped. Condensate has a high heat content. Condensate is a readily available, economical feedwater source. Properly treated, it is very pure. Condensate improves feedwater quality and reduces makeup water demand and pretreatment costs. Higher quality feedwater means more reliable boiler operation

An experimental study of high pressure steam condensation in a vertical tube of passive secondary condensation system

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang Jae; No, Hee Cheon [KAIST, Taejon (Korea, Republic of)

1998-07-01

To investigate the physical parameters of PSCS (Passive Secondary Condensation System) which is a passive residual heat removal system of CP-1300, the high pressure condensation experiments are performed in a small scale experimental facility. The experimental parameters are the local heat flux and the transfer coefficient and the pressure drop in a condensation heat trasnfer. The film condensation heat transfer coefficients in a vertical tube are calculated from the measured wall temperature difference and compared with the analytical models. A new analytical condensation model is developed based on the annular film flow model. The present model gives marginally better results than those from the Shah model in comparison with the experimental data in the database. Also, experimental data are compared with the results of the RELAP5/MOD3.2 thermal hydraulic code. The RELAP5/MOD3.2 underpredicts the condensation heat transfer coefficients of the present experiment by 50 %.

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

International Nuclear Information System (INIS)

Coenenberg, J.G.

1997-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

Energy Technology Data Exchange (ETDEWEB)

Coenenberg, J.G.

1997-08-15

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

Use of fundamental condensation heat transfer experiments for the development of a sub-grid liquid jet condensation model

Energy Technology Data Exchange (ETDEWEB)

Buschman, Francis X., E-mail: Francis.Buschman@unnpp.gov; Aumiller, David L.

2017-02-15

Highlights: • Direct contact condensation data on liquid jets up to 1.7 MPa in pure steam and in the presence of noncondensable gas. • Identified a pressure effect on the impact of noncondensables to suppress condensation heat transfer not captured in existing data or correlations. • Pure steam data is used to develop a new correlation for condensation heat transfer on subcooled liquid jets. • Noncondensable data used to develop a modification to the renewal time estimate used in the Young and Bajorek correlation for condensation suppression in the presence of noncondensables. • A jet injection boundary condition, using a sub-grid jet condensation model, is developed for COBRA-IE which provides a more detailed estimate of the condensation rate on the liquid jet and allows the use of jet specific closure relationships. - Abstract: Condensation on liquid jets is an important phenomenon for many different facets of nuclear power plant transients and analyses such as containment spray cooling. An experimental facility constructed at the Pennsylvania State University, the High Pressure Liquid Jet Condensation Heat Transfer facility (HPLJCHT), has been used to perform steady-state condensation heat transfer experiments in which the temperature of the liquid jet is measured at different axial locations allowing the condensation rate to be determined over the jet length. Test data have been obtained in a pure steam environment and with varying concentrations of noncondensable gas. This data extends the available jet condensation data from near atmospheric pressure up to a pressure of 1.7 MPa. An empirical correlation for the liquid side condensation heat transfer coefficient has been developed based on the data obtained in pure steam. The data obtained with noncondensable gas were used to develop a correlation for the renewal time as used in the condensation suppression model developed by Young and Bajorek. This paper describes a new sub-grid liquid jet

Use of fundamental condensation heat transfer experiments for the development of a sub-grid liquid jet condensation model

International Nuclear Information System (INIS)

Buschman, Francis X.; Aumiller, David L.

2017-01-01

Highlights: • Direct contact condensation data on liquid jets up to 1.7 MPa in pure steam and in the presence of noncondensable gas. • Identified a pressure effect on the impact of noncondensables to suppress condensation heat transfer not captured in existing data or correlations. • Pure steam data is used to develop a new correlation for condensation heat transfer on subcooled liquid jets. • Noncondensable data used to develop a modification to the renewal time estimate used in the Young and Bajorek correlation for condensation suppression in the presence of noncondensables. • A jet injection boundary condition, using a sub-grid jet condensation model, is developed for COBRA-IE which provides a more detailed estimate of the condensation rate on the liquid jet and allows the use of jet specific closure relationships. - Abstract: Condensation on liquid jets is an important phenomenon for many different facets of nuclear power plant transients and analyses such as containment spray cooling. An experimental facility constructed at the Pennsylvania State University, the High Pressure Liquid Jet Condensation Heat Transfer facility (HPLJCHT), has been used to perform steady-state condensation heat transfer experiments in which the temperature of the liquid jet is measured at different axial locations allowing the condensation rate to be determined over the jet length. Test data have been obtained in a pure steam environment and with varying concentrations of noncondensable gas. This data extends the available jet condensation data from near atmospheric pressure up to a pressure of 1.7 MPa. An empirical correlation for the liquid side condensation heat transfer coefficient has been developed based on the data obtained in pure steam. The data obtained with noncondensable gas were used to develop a correlation for the renewal time as used in the condensation suppression model developed by Young and Bajorek. This paper describes a new sub-grid liquid jet

Hazardous waste treatment facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1993-01-01

To centralize treatment, storage, and staging areas for hazardous wastes, Los Alamos National Laboratory has designed a 12,000-ft 2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks, bulking small organic waste volumes, processing scintillation vials, treating reactives such as lithium hydride and pyrophoric uranium, treating contaminated solids such as barium sand, and treating plating wastes. The treated wastes will then be appropriately disposed of. This report describes the integral features of the hazardous waste treatment facility

Preoperational test report, primary ventilation condensate system

Energy Technology Data Exchange (ETDEWEB)

Clifton, F.T.

1997-01-29

Preoperational test report for Primary Ventilation Condensate System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system provides a collection point for condensate generated by the W-030 primary vent offgas cooling system serving tanks AYIOI, AY102, AZIOI, AZI02. The system is located inside a shielded ventilation equipment cell and consists of a condensate seal pot, sampling features, a drain line to existing Catch Tank 241-AZ-151, and a cell sump jet pump. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.

Modeling bubble condenser containment with computer code COCOSYS: post-test calculations of the main steam line break experiment at ELECTROGORSK BC V-213 test facility

International Nuclear Information System (INIS)

Lola, I.; Gromov, G.; Gumenyuk, D.; Pustovit, V.; Sholomitsky, S.; Wolff, H.; Arndt, S.; Blinkov, V.; Osokin, G.; Melikhov, O.; Melikhov, V.; Sokoline, A.

2005-01-01

Containment of the WWER-440 Model 213 nuclear power plant features a Bubble Condenser, a complex passive pressure suppression system, intended to limit pressure rise in the containment during accidents. Due to lack of experimental evidence of its successful operation in the original design documentation, the performance of this system under accidents with ruptures of large high-energy pipes of the primary and secondary sides remains a known safety concern for this containment type. Therefore, a number of research and analytical studies have been conducted by the countries operating WWER-440 reactors and their Western partners in the recent years to verify Bubble Condenser operation under accident conditions. Comprehensive experimental research studies at the Electrogorsk BC V-213 test facility, commissioned in 1999 in Electrogorsk Research and Engineering Centre (EREC), constitute essential part of these efforts. Nowadays this is the only operating large-scale facility enabling integral tests on investigation of the Bubble Condenser performance. Several large international research projects, conducted at this facility in 1999-2003, have covered a spectrum of pipe break accidents. These experiments have substantially improved understanding of the overall system performance and thermal hydraulic phenomena in the Bubble Condenser Containment, and provided valuable information for validating containment codes against experimental results. One of the recent experiments, denoted as SLB-G02, has simulated steam line break. The results of this experiment are of especial value for the engineers working in the area of computer code application for WWER-440 containment analyses, giving an opportunity to verify validity of the code predictions and identify possibilities for model improvement. This paper describes the results of the post-test calculations of the SLB-G02 experiment, conducted as a joint effort of GRS, Germany and Ukrainian technical support organizations for

Assessment of RELAP5/MOD3 with condensation experiment for pure steam condensation in a vercal tube

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang Jae; No, Hee Cheon [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1999-12-31

The film condensation models in RELAP5/MOD3.1 and RELAP5/MOD3.2 are assessed with the data of experiment performed in the scaled down condensation experimental facility with a single vertical tube of inner diameter of 46 mm in the range of pressure 0.1 {approx} 7.5 MPa for the PSCS(Passive Secondary Condenser System). Both MOD3.1 and MOD3.2 don`t shows any reliable predictions of the experimental data. The RELAP5/MOD3.1 overpredicts the heat transfer coefficients of experiment, whereas the RELAP5/MOD3.2 underpredicts those data. It is recommended that the film condensation model in RELAP5/MOD3.2 should be modified to have a larger heat transfer coefficient than those of the present model to give the reliable predictions. 7 refs., 6 figs., 1 tab. (Author)

Assessment of RELAP5/MOD3 with condensation experiment for pure steam condensation in a vercal tube

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang Jae; No, Hee Cheon [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1998-12-31

The film condensation models in RELAP5/MOD3.1 and RELAP5/MOD3.2 are assessed with the data of experiment performed in the scaled down condensation experimental facility with a single vertical tube of inner diameter of 46 mm in the range of pressure 0.1 {approx} 7.5 MPa for the PSCS(Passive Secondary Condenser System). Both MOD3.1 and MOD3.2 don`t shows any reliable predictions of the experimental data. The RELAP5/MOD3.1 overpredicts the heat transfer coefficients of experiment, whereas the RELAP5/MOD3.2 underpredicts those data. It is recommended that the film condensation model in RELAP5/MOD3.2 should be modified to have a larger heat transfer coefficient than those of the present model to give the reliable predictions. 7 refs., 6 figs., 1 tab. (Author)

Hazard Baseline Downgrade Effluent Treatment Facility

International Nuclear Information System (INIS)

Blanchard, A.

1998-01-01

This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility

Conceptual design of the test facility for the two-phase critical flow with non-condensable gas

Energy Technology Data Exchange (ETDEWEB)

Chang, Seok Kyu; Chung, Chang Hwan

2000-12-01

The two-phase critical flow test with non-condensible gas is for the simulation of the critical flow phenomena which can be occurred during SB-LOCA on SMART reactor. The requirements of the critical flow test are 7{approx}20mm pipe break dia., 7{approx}12MPa stagnation pressure, 0{approx}60 deg C subcooling degree and 0{approx}0.5kg/s N2 gas flow rate. For the satisfaction of these requirements on the test facility, critical flow rates were calculated with various models. With the selected reference pressure vessel(1.3m{sup 3}), the conceptual design of the test facility was performed. The important components of the test facility are the pressure vessel which has main circulation line, the test section attached to the bottom of the pressure vessel, suppression tank, the N2 gas supply tanks for maintaining the system pressure and N2 gas flow rate at test section and the auxiliary N2 gas converting system. For the measurements of the critical flow rate, flowmeter and level gauge is installed at the upstream of the test section and the pressure vessel, respectively. The realtime pressure control system is installed at the entrance of the pressure vessel for maintaining the system pressure and the N2 gas flow regulating system is also installed at the upstream of the test section. The design of the control and monitoring system for the operation of the test facility and the DAS for acquiring the test data were also performed. The conceptual operating process of the test facility was determined.

Conceptual design of the test facility for the two-phase critical flow with non-condensable gas

International Nuclear Information System (INIS)

Chang, Seok Kyu; Chung, Chang Hwan

2000-12-01

The two-phase critical flow test with non-condensible gas is for the simulation of the critical flow phenomena which can be occurred during SB-LOCA on SMART reactor. The requirements of the critical flow test are 7∼20mm pipe break dia., 7∼12MPa stagnation pressure, 0∼60 deg C subcooling degree and 0∼0.5kg/s N2 gas flow rate. For the satisfaction of these requirements on the test facility, critical flow rates were calculated with various models. With the selected reference pressure vessel(1.3m 3 ), the conceptual design of the test facility was performed. The important components of the test facility are the pressure vessel which has main circulation line, the test section attached to the bottom of the pressure vessel, suppression tank, the N2 gas supply tanks for maintaining the system pressure and N2 gas flow rate at test section and the auxiliary N2 gas converting system. For the measurements of the critical flow rate, flowmeter and level gauge is installed at the upstream of the test section and the pressure vessel, respectively. The realtime pressure control system is installed at the entrance of the pressure vessel for maintaining the system pressure and the N2 gas flow regulating system is also installed at the upstream of the test section. The design of the control and monitoring system for the operation of the test facility and the DAS for acquiring the test data were also performed. The conceptual operating process of the test facility was determined

Facility for processing the condensates from nuclear power plants (BWR and PWR)

International Nuclear Information System (INIS)

Lucker, Georges.

1975-01-01

A plant for the processing of the condensates from boiling water or pressurized water nuclear power plants is presented. A series of couples of units for the processing of the condensates through mixed beds of ion exchange resins simultaneously ensures the filtration and demineralization of the condensates. When the resins are saturated, each mixed bed is transferred into a unit of regeneration of said resins. Each processing unit is a sphere made of a stainless material, and provided with a plurality of air and water pipes allowing the admission and evacuation of the various elements to be successively controlled [fr

Confirmatory tests of full-scale condensers for SBWR

International Nuclear Information System (INIS)

Masoni, P.; Botti, S.; Fitzsimmons, G.W.

1993-01-01

A full-scale isolation condenser and a full-scale passive containment cooling condenser for the Simplified Boiling Water Reactor (SBWR) will be tested to confirm the thermal-hydraulic and structural design characteristics of these components. The condensers provide vital roles in removing heat from the reactor vessel and the containment during certain design basis events. This paper describes the condensers and the test facilities which are under construction and summarizes the test objectives, the planned instrumentation, and the conditions to be tested. The results of some pre-test performance predictions, calculated with the TRACG code are presented. The results of the testing program are expected to demonstrate that the condenser designs will provide the required heat removal capacity and will survive the design basis temperature/pressure cycles without structural damage

Packaging, Transportation and Recycling of NPP Condenser Modules - 12262

Energy Technology Data Exchange (ETDEWEB)

Polley, G.M. [Perma-Fix Environmental Services, 575 Oak Ridge Turnpike, Oak Ridge, TN 37830 (United States)

2012-07-01

Perma-Fix was awarded contract from Energy Northwest for the packaging, transportation and disposition of the condenser modules, water boxes and miscellaneous metal, combustibles and water generated during the 2011 condenser replacement outage at the Columbia Generating Station. The work scope was to package the water boxes and condenser modules as they were removed from the facility and transfer them to the Perma-Fix Northwest facility for processing, recycle of metals and disposition. The condenser components were oversized and overweight (the condenser modules weighed ∼102,058 kg [225,000 lb]) which required special equipment for loading and transport. Additional debris waste was packaged in inter-modals and IP-1 boxes for transport. A waste management plan was developed to minimize the generation of virtually any waste requiring landfill disposal. The Perma-Fix Northwest facility was modified to accommodate the ∼15 m [50-ft] long condenser modules and equipment was designed and manufactured to complete the disassembly, decontamination and release survey. The condenser modules are currently undergoing processing for free release to a local metal recycler. Over three millions pounds of metal will be recycled and over 95% of the waste generated during this outage will not require land disposal. There were several elements of this project that needed to be addressed during the preparation for this outage and the subsequent packaging, transportation and processing. - Staffing the project to support 24/7 generation of large components and other wastes. - The design and manufacture of the soft-sided shipping containers for the condenser modules that measured ∼15 m X 4 m X 3 m [50 ft X 13 ft X 10 ft] and weighed ∼102,058 kg [225,000 lbs] - Developing a methodology for loading the modules into the shipping containers. - Obtaining a transport vehicle for the modules. - Designing and modifying the processing facility. - Movement of the modules at the processing

Experimental Investigation of Flow Condensation in Microgravity

Science.gov (United States)

Lee, Hyoungsoon; Park, Ilchung; Konishi, Christopher; Mudawar, Issam; May, Rochelle I.; Juergens, Jeffery R.; Wagner, James D.; Hall, Nancy R.; Nahra, Henry K.; Hasan, Mohammed M.;

Hanford facilities tracer study report (315 Water Treatment Facility)

International Nuclear Information System (INIS)

Ambalam, T.

1995-01-01

This report presents the results and findings of a tracer study to determine contact time for the disinfection process of 315 Water Treatment Facility that supplies sanitary water for the 300 Area. The study utilized fluoride as the tracer and contact times were determined for two flow rates. Interpolation of data and short circuiting effects are also discussed. The 315 Water Treatment Facility supplies sanitary water for the 300 Area to various process and domestic users. The Surface Water Treatment Rule (SWTR), outlined in the 1986 Safe Drinking Water Act Amendments enacted by the EPA in 1989 and regulated by the Washington State Department of Health (DOH) in Section 246-290-600 of the Washington Administrative Code (WAC), stipulates filtration and disinfection requirements for public water systems under the direct influence of surface water. The SWTR disinfection guidelines require that each treatment system achieves predetermined inactivation ratios. The inactivation by disinfection is approximated with a measure called CxT, where C is the disinfectant residual concentration and T is the effective contact time of the water with the disinfectant. The CxT calculations for the Hanford water treatment plants were derived from the total volume of the contact basin(s). In the absence of empirical data to support CxT calculations, the DOH determined that the CxT values used in the monthly reports for the water treatment plants on the Hanford site were invalid and required the performance of a tracer study at each plant. In response to that determination, a tracer study will be performed to determine the actual contact times of the facilities for the CxT calculations

Nuclear fuel treatment facility for 'Mutsu'

International Nuclear Information System (INIS)

Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

1989-01-01

A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

Advanced treatment of flue gas condensate; Avancerad rening av roekgaskondensat

Energy Technology Data Exchange (ETDEWEB)

Axby, Fredrik [Carl Bro Energikonsult AB, Malmoe (Sweden); Ekengren, Oesten; Bjurhem, Jan Erik [IVL Swedish Environmental Research Inst. (Sweden)

2004-11-01

The aim of the project is to study different techniques to recover water to the process and to reduce emission of ammonia to water and air. Membrane technology (ultra- (UF) and nanofiltration (NF) and reverse osmosis (RO)) and a stripper have been studied for ammonia separation. The use of bio-fuel in energy production is increasing. The off-gases are often condensed to increase energy yield and to decrease emissions to air. Since the concentration of nitrogen (ammonium) is high in condensates from units with SNCR for NO{sub x}-reduction (selective non-catalytic reduction) this water has to be treated further. Another aim of the project is to replace a great part of the tap water used in the process. This can be accomplished with membrane technology. Laboratory tests revealed a certain degree of membrane fouling. However, both NF and RO worked well in the full-scale unit, in spite of problems in the condensate treatment that resulted in tar products in the water. There was no obvious negative effect on these membranes. Analyses of PAH have shown a low base concentration that may lead to fouling after a long time. UF removes most of these PAH and thus protects the following NF- or RO-membranes. NF gave about 3 times higher filtration capacity (flux) than RO for the condensate at 30 bars. This can save a lot of money, since the membrane area can be reduced to a third. High temperature also increases the flux. The results are of high interest but ought to be certified during long run tests. Fouling was low in both NF and RO, and initial flux was retained after cleaning. The reason is probably the good pre-treatment (UF). The concentration could proceed very far, which make it possibly to reuse the concentrate to the system. Simulations of an ammonia stripper showed some parameters to be critical in certain ranges, while others didn't affect the result. Airflow is a critical parameter during stable conditions within the design data. Simulated data were verified

Wastewater treatment facilities: Energy efficient improvements and cogeneration

International Nuclear Information System (INIS)

Kunkle, R.; Gray, R.; Delzel, D.

1992-10-01

The Washington State Energy Office (WSEO) has worked with both the Bonneville Power Administration (BPA) and the US Department of Energy to provide technical and financial assistance to local governments. Based on a recent study conducted by Ecotope for WSEO, local governments spend an estimated $45 million on utility bills statewide. Water and wastewater facilities account for almost a third of this cost. As a result, WSEO decided to focus its efforts on the energy intensive water and wastewater sector. The ultimate goal of this project was to develop mechanisms to incorporate energy efficiency improvements into wastewater treatment facilities in retrofits and during upgrades, remodels, and new construction. Project activities included the following: The review of the existing regulatory environment for treatment system construction, A summary of financing options for efficiency improvements in treatment facilities, A literature review of energy efficiency opportunities in treatment plants, Survey and site visits to characterize existing facilities in Washington State, Estimates of the energy efficiency and cogeneration potential in the sector, and A case study to illustrate the implementation of an efficiency improvement in a treatment facility

Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

International Nuclear Information System (INIS)

WESTRA, A.G.

1999-01-01

This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility

Effluent Treatment Facility tritium emissions monitoring

International Nuclear Information System (INIS)

Dunn, D.L.

1991-01-01

An Environmental Protection Agency (EPA) approved sampling and analysis protocol was developed and executed to verify atmospheric emissions compliance for the new Savannah River Site (SRS) F/H area Effluent Treatment Facility. Sampling equipment was fabricated, installed, and tested at stack monitoring points for filtrable particulate radionuclides, radioactive iodine, and tritium. The only detectable anthropogenic radionuclides released from Effluent Treatment Facility stacks during monitoring were iodine-129 and tritium oxide. This paper only examines the collection and analysis of tritium oxide

Preoperational test report, recirculation condenser cooling systems

Energy Technology Data Exchange (ETDEWEB)

Clifton, F.T.

1997-11-04

This represents a preoperational test report for Recirculation Condenser Systems, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The four system provide condenser cooling water for vapor space cooling of tanks AY1O1, AY102, AZ1O1, AZ102. Each system consists of a valved piping loop, a pair of redundant recirculation pumps, a closed-loop evaporative cooling tower, and supporting instrumentation; equipment is located outside the farm on concrete slabs. Piping is routed to the each ventilation condenser inside the farm via below-grade concrete trenches. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.

Preoperational test report, recirculation condenser cooling systems

International Nuclear Information System (INIS)

Clifton, F.T.

1997-01-01

This represents a preoperational test report for Recirculation Condenser Systems, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The four system provide condenser cooling water for vapor space cooling of tanks AY1O1, AY102, AZ1O1, AZ102. Each system consists of a valved piping loop, a pair of redundant recirculation pumps, a closed-loop evaporative cooling tower, and supporting instrumentation; equipment is located outside the farm on concrete slabs. Piping is routed to the each ventilation condenser inside the farm via below-grade concrete trenches. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System

Grout Treatment Facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) is an existing treatment, storage, and/or disposal (TSD) unit located in the 200 East Area and the adjacent 600 Area of the Hanford Site. The GTF mixes dry cementitious solids with liquid mixed waste (containing both dangerous and radioactive constituents) produced by Hanford Site operations. The GTF consists of the following: The 241-AP-02D and 241-AP-04D waste pump pits and transfer piping; Dry Materials Facility (DMF); Grout Disposal Facility (GDF), consisting of the disposal vault and support and monitoring equipment; and Grout Processing Facility (GPF) and Westinghouse Hanford Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The Grout Treatment Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this TSD unit, including the current revision, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings

Specific interactions versus counterion condensation. 2. Theoretical treatment within the counterion condensation theory.

Science.gov (United States)

Donati, Ivan; Benegas, Julio C; Cesàro, Attilio; Paoletti, Sergio

2006-05-01

Polyuronates such as pectate and alginate are very well-known examples of biological polyelectrolytes undergoing, upon addition of divalent cations, an interchain association that acts as the junction of an eventually formed stable hydrogel. In the present paper, a thermodynamic model based on the counterion condensation theory has been developed to account for this cation-induced chain pairing of negatively charged polyelectrolytes. The strong interactions between cross-linking ions and uronate moieties in the specific binding site have been described in terms of chemical bonding, with complete charge annihilation between the two species. The chain-pairing process is depicted as progressively increasing with the concentration of cross-linking counterions and is thermodynamically defined by the fraction of each species. On these bases, the total Gibbs energy of the system has been expressed as the sum of the contributions of the Gibbs energy of the (single) chain stretches and of the (associated) dimers, weighted by their respective fractions 1 - theta and theta. In addition, the model assumes that the condensed divalent counterions exhibit an affinity free-energy for the chain, G(C)(aff,0), and the junction, G(D)(aff,0), respectively. Moreover, a specific Gibbs energy of chemical bonding, G(bond,0), has been introduced as the driving force for the formation of dimers. The model provides the mathematical formalism for calculating the fraction, theta, of chain dimers formed and the amount of ions condensed and bound onto the polyelectrolyte when two different types of counterions (of equal or different valence) are present. The effect of the parameter G(bond,0) has been investigated and, in particular, its difference from G(C,D)(aff,0) was found to be crucial in determining the distribution of the ions into territorial condensation and chemical bonding, respectively. Finally, the effect of the variation of the molar ratio between cross-linking ions and uronic groups

Influence of the distribution of non-condensables on passive containment condenser performance in PANDA

International Nuclear Information System (INIS)

Bandurski, Th.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G.

2001-01-01

Recently passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large-scale PANDA facility. The PANDA tests achieved the dual objectives of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the system, and extending the database available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam non-condensable gases, as well as a variety of asymmetric and challenging start-up conditions. The present paper addresses the transient distribution of non-condensables in PANDA, and their effect on (passive) condenser performance. (author)

Influence of the distribution of non-condensables on passive containment condenser performance in PANDA

Energy Technology Data Exchange (ETDEWEB)

Bandurski, Th.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G

2001-03-01

Recently passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large-scale PANDA facility. The PANDA tests achieved the dual objectives of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the system, and extending the database available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam non-condensable gases, as well as a variety of asymmetric and challenging start-up conditions. The present paper addresses the transient distribution of non-condensables in PANDA, and their effect on (passive) condenser performance. (author)

Lesson learned from the SARNET wall condensation benchmarks

International Nuclear Information System (INIS)

Ambrosini, W.; Forgione, N.; Merli, F.; Oriolo, F.; Paci, S.; Kljenak, I.; Kostka, P.; Vyskocil, L.; Travis, J.R.; Lehmkuhl, J.; Kelm, S.; Chin, Y.-S.; Bucci, M.

2014-01-01

Highlights: • The results of the benchmarking activity on wall condensation are reported. • The work was performed in the frame of SARNET. • General modelling techniques for condensation are discussed. • Results of University of Pisa and of other benchmark participants are discussed. • The lesson learned is drawn. - Abstract: The prediction of condensation in the presence of noncondensable gases has received continuing attention in the frame of the Severe Accident Research Network of Excellence, both in the first (2004–2008) and in the second (2009–2013) EC integrated projects. Among the different reasons for considering so relevant this basic phenomenon, coped with by classical treatments dated in the first decades of the last century, there is the interest for developing updated CFD models for reactor containment analysis, requiring validating at a different level the available modelling techniques. In the frame of SARNET, benchmarking activities were undertaken taking advantage of the work performed at different institutions in setting up and developing models for steam condensation in conditions of interest for nuclear reactor containment. Four steps were performed in the activity, involving: (1) an idealized problem freely inspired at the actual conditions occurring in an experimental facility, CONAN, installed at the University of Pisa; (2) a first comparison with experimental data purposely collected by the CONAN facility; (3) a second comparison with data available from experimental campaigns performed in the same apparatus before the inclusion of the activities in SARNET; (4) a third exercise involving data obtained at lower mixture velocity than in previous campaigns, aimed at providing conditions closer to those addressed in reactor containment analyses. The last step of the benchmarking activity required to change the configuration of the experimental apparatus to achieve the lower flow rates involved in the new test specifications. The

Experimental facility with two-phase flow and with high concentration of non-condensable gases for research and development of emergency cooling system of advanced nuclear reactors

International Nuclear Information System (INIS)

Macedo, Luiz Alberto; Baptista Filho, Benedito Dias

2006-01-01

The development of emergency cooling passive systems of advanced nuclear reactors requires the research of some relative processes to natural circulation, in two-phase flow conditions involving condensation processes in the presence of non-condensable gases. This work describes the main characteristics of the experimental facility called Bancada de Circulacao Natural (BCN), designed for natural circulation experiments in a system with a hot source, electric heater, a cold source, heat exchanger, operating with two-phase flow and with high concentration of noncondensable gas, air. The operational tests, the data acquisition system and the first experimental results in natural circulation are presented. The experiments are transitory in natural circulation considering power steps. The distribution of temperatures and the behavior of the flow and of the pressure are analyzed. The experimental facility, the instrumentation and the data acquisition system demonstrated to be adapted for the purposes of research of emergency cooling passive systems, operating with two-phase flow and with high concentration of noncondensable gases. (author)

A Study on Condensation Heat Transfer at the Exterior Surface of S.A.M. Coated Titanium Tube Using in Steam Condensers

Energy Technology Data Exchange (ETDEWEB)

Im, Sung-Gu; Lee, Sang-Hyup; Ji, Dae-Yun; Park, Hyun-Gyu; Lee, Kwon-Yeong [Handong Global University, Pohang (Korea, Republic of)

2016-10-15

Condensation occurs when the temperature of a steam is reduced below its saturation temperature. There exist two forms of condensation on cooling surface: dropwise, and film condensations. Usually, dropwise condensation has a better heat transfer performance than film condensation, but it has limit of short period. Ma et al. executed heat transfer experiment in dropwise condensation with non-condensable gas, and studied how the amount of air and pressure difference affect condensation heat transfer coefficient. The more non-condensable gas exist, the condensation heat transfer coefficient is decreased. As a result, surface modified brass tube and stainless tube showed higher condensation heat transfer coefficient as much as 1.3 and 1.4 times comparing with their bare tubes in 70 kPa vacuum condition respectively. Most of power plants use sea water as coolant, so the surface of metal tubes could be corroded by the coolant. We had researched an experimental study related to condensation heat transfer on surface modified titanium tube. Our experimental facility was designed to show how two kinds of tube's heat transfer performances are different in a same condition. We changed the range of saturation pressure and coolant flow rate to observe tube's performance change. When saturation pressure and coolant flow rate increase, overall heat transfer coefficients were increased. When residue of non-condensable gases was decreased, the overall heat transfer coefficients were increased. S.A.M. coated tube's overall heat transfer coefficients were lower than those of bare tube, because the droplets didn't have a tendency of frequently falling down.

Pain treatment facilities: do we need quantity or quality?

NARCIS (Netherlands)

de Meij, N.; Koke, A.; van der Weijden, T.; van Kleef, M.; Patijn, J.

2014-01-01

Rationale, aims and objectives: Chronic pain patients referred to a pain treatment facility have no guarantee that they will receive a proper diagnostic procedure or treatment. To obtain information about organizational aspects of pain treatment facilities and the content of their daily pain

CFD simulation on condensation inside a Hybrid SIT

Energy Technology Data Exchange (ETDEWEB)

Jeon, Byong Guk; Ryu, Sung Uk; Kim, Seok; Euh, Dong Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

The concept of Hybrid Safety Injection Tank system (Hybrid SIT) was proposed by Korea Atomic Energy Research Institute (KAERI) aiming at Advanced Power Reactor Plus. The main advantage of the system is the ready injection of coolant into the reactor coolant system at high pressure. In this paper, a CFD simulation is conducted as a preliminary study. In Hybrid SITs, condensation inside the tank affects its pressure rise and injection time. In an attempt to explore the condensation in detail, we manufactured a dedicated experimental facility for visualization of condensation-induced thermal mixing and conducted a preliminary CFD simulation. Its condensation models were validated first and then computational domain was constructed. The water region was modeled as a solid for stable calculation. The CFD results gave less condensation and excessive pressurization because of lack of steam penetration into the water. In the future, the water region will be modeled as liquid using a VOF model.

Freshwater Treatment and Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The Freshwater Treatment and Test Facility, located at SANGB, has direct year-round access to water from Lake St. Clair and has a State of Michigan approved National...

Preliminary Analysis of Rapid Condensation Experiment with MARS-KS Code

Energy Technology Data Exchange (ETDEWEB)

Bae, Jae Ho; Jun, Hwang Yong; Jeong, Hae Yong [Sejong University, Seoul (Korea, Republic of)

2016-05-15

In the present study, the rapid condensation experiment performed in MANOTEA facility is analyzed with the MARS-KS code. It is known that there exists some limitation with a system code to predict this kind of a very active condensation due to direct mixing of cold injection flow and steam. Through the analysis we investigated the applicability of MARS-KS code for the design of various passive safety systems in the future. The configuration of the experimental facility MANOTEA, which has been constructed at the University of Maryland - United States Naval Academy, is described and the modeling approach using the MARS-KS code is also provided. The preliminary result shows that the MARS-KS predicts the general trend of pressure and temperature in the condensing part correctly. However, it is also found that there exist some limitations in the simulation such as an unexpected pressure peak or a sudden temperature change.

Experiments of condensation-induced water hammers at the UniBw Munich

International Nuclear Information System (INIS)

Dirndorfer, Stefan; Kulisch, Helmut; Malcherek, Andreas

2013-01-01

Condensation-induced water hammers belong to the most serious and complex pressure surges. Experimental data from literature are scanty, incomplete, not public or simply missing. A new test facility at the UniBw (University of the German Armed Forces) was constructed to perform own experiments within a research alliance. This new test facility uses a complete new approach. In contrast to other test stations, the UniBw water hammer test facility is a closed system. This leads on the one hand to a more complex handling with respect of conducting experiments but on the other hand also to a more realistic characterization of thermo-hydraulic phenomena which can occur in a power plant. The first results of a measured condensation-induced water hammer are presented. (orig.)

Experiments of condensation-induced water hammers at the UniBw Munich

Energy Technology Data Exchange (ETDEWEB)

Dirndorfer, Stefan; Kulisch, Helmut; Malcherek, Andreas [Universitaet der Bundeswehr Muenchen, Neubiberg (Germany). Hydromechanik und Wasserbau

2013-03-15

Condensation-induced water hammers belong to the most serious and complex pressure surges. Experimental data from literature are scanty, incomplete, not public or simply missing. A new test facility at the UniBw (University of the German Armed Forces) was constructed to perform own experiments within a research alliance. This new test facility uses a complete new approach. In contrast to other test stations, the UniBw water hammer test facility is a closed system. This leads on the one hand to a more complex handling with respect of conducting experiments but on the other hand also to a more realistic characterization of thermo-hydraulic phenomena which can occur in a power plant. The first results of a measured condensation-induced water hammer are presented. (orig.)

Antifoam Degradation Products in Off Gas and Condensate of Sludge Batch 9 Simulant Nitric-Formic Flowsheet Testing for the Defense Waste Processing Facility

Energy Technology Data Exchange (ETDEWEB)

Smith, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-04-14

Ten chemical processing cell (CPC) experiments were performed using simulant to evaluate Sludge Batch 9 for sludge-only and coupled processing using the nitric-formic flowsheet in the Defense Waste Processing Facility (DWPF). Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) cycles were performed on eight of the ten. The other two were SRAT cycles only. Samples of the condensate, sludge, and off gas were taken to monitor the chemistry of the CPC experiments. The Savannah River National Laboratory (SRNL) has previously shown antifoam decomposes to form flammable organic products, (hexamethyldisiloxane (HMDSO), trimethylsilanol (TMS), and propanal), that are present in the vapor phase and condensate of the CPC vessels. To minimize antifoam degradation product formation, a new antifoam addition strategy was implemented at SRNL and DWPF to add antifoam undiluted.

Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

Energy Technology Data Exchange (ETDEWEB)

Graf, F.A. Jr.

1995-02-27

This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System`s pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System.

Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

International Nuclear Information System (INIS)

Graf, F.A. Jr.

1995-01-01

This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System's pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System

Pain treatment facilities: do we need quantity or quality?

Science.gov (United States)

de Meij, Nelleke; Köke, Albère; van der Weijden, Trudy; van Kleef, Maarten; Patijn, Jacob

2014-10-01

Chronic pain patients referred to a pain treatment facility have no guarantee that they will receive a proper diagnostic procedure or treatment. To obtain information about organizational aspects of pain treatment facilities and the content of their daily pain practice, we performed a questionnaire survey. The aim of the study was to evaluate the amount of pain treatment facilities, the content of organized specialized pain care and adherence to the criteria of the internationally accepted guidelines for pain treatment services. The University Pain Centre Maastricht in the Department of Anaesthesiology and Pain Management at Maastricht University Medical Centre developed a questionnaire survey based on the Recommendations for Pain Treatment Services of the International Association for the Study of Pain (IASP). The questionnaire was sent to the medical boards of all hospitals in the Netherlands (n=94). The response rate was 86% (n=81). Of all hospitals, 88.9% (n=72) reported the provision of organized specialized pain care, which was provided by a pain management team in 86.1% (n=62) and by an individual specialist in 13.9% (n=10). Insight was obtained from pain treatment facilities in five different domains: the organizational structure of pain management, composition of the pain team, pain team practice, patient characteristics, and research and education facilities. Although 88.9% of all hospitals stated that organized specialized pain care was provided, only a few hospitals could adhere to the criteria for pain treatment services of the IASP. The outcome of the questionnaire survey may help to define quality improvement standards for pain treatment facilities. © 2014 John Wiley & Sons, Ltd.

Use of ORELA to produce neutrons for scattering studies on condensed matter

International Nuclear Information System (INIS)

Peelle, R.W.; Lewis, T.A.; Mihalczo, J.T.; Mook, H.A.; Moon, R.M.

1975-09-01

The Oak Ridge Electron Linear Accelerator (ORELA) is evaluated as a source of neutrons for condensed matter research. Two options are assessed: (1) use of the present target arrangement with minor modifications; and (2) the construction of a new target and experiment facility designed for condensed matter research and equipped with a subcritical fission booster. The expected source strength and time behavior are discussed, including the fundamentals of moderator design. The effect on the programs presently using the linac are considered. It is concluded that a special-purpose neutron source facility using pulsed electrons from ORELA and containing a subcritical booster could be built to make a cost-effective neutron scattering facility of great power and utility. (auth)

Region 9 NPDES Facilities - Waste Water Treatment Plants

Science.gov (United States)

Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

Condensation model for the ESBWR passive condensers

International Nuclear Information System (INIS)

Revankar, S. T.; Zhou, W.; Wolf, B.; Oh, S.

2012-01-01

In the General Electric's Economic simplified boiling water reactor (GE-ESBWR) the passive containment cooling system (PCCS) plays a major role in containment pressure control in case of an loss of coolant accident. The PCCS condenser must be able to remove sufficient energy from the reactor containment to prevent containment from exceeding its design pressure following a design basis accident. There are three PCCS condensation modes depending on the containment pressurization due to coolant discharge; complete condensation, cyclic venting and flow through mode. The present work reviews the models and presents model predictive capability along with comparison with existing data from separate effects test. The condensation models in thermal hydraulics code RELAP5 are also assessed to examine its application to various flow modes of condensation. The default model in the code predicts complete condensation well, and basically is Nusselt solution. The UCB model predicts through flow well. None of condensation model in RELAP5 predict complete condensation, cyclic venting, and through flow condensation consistently. New condensation correlations are given that accurately predict all three modes of PCCS condensation. (authors)

Transformation of Litchi Pericarp-Derived Condensed Tannin with Aspergillus awamori

Directory of Open Access Journals (Sweden)

Sen Lin

2016-07-01

Full Text Available Condensed tannin is a ubiquitous polyphenol in plants that possesses substantial antioxidant capacity. In this study, we have investigated the polyphenol extraction recovery and 2,2-diphenyl-1-picrylhydrazyl (DPPH scavenging activity of the extracted polyphenol after litchi pericarp is treated with Aspergillus awamori, Aspergillus sojae or Aspergillus oryzae. We have further explored the activity of A. awamori in the formation of condensed tannin. The treatment of A. awamori appeared to produce the highest antioxidant activity of polyphenol from litchi pericarp. Further studies suggested that the treatment of A. awamori releases the non-extractable condensed tannin from cell walls of litchi pericarp. The total extractable tannin in the litchi pericarp residue after a six-time extraction with 60% ethanol increased from 199.92 ± 14.47–318.38 ± 7.59 μg/g dry weight (DW after the treatment of A. awamori. The ESI-TOF-MS and HPLC-MS2 analyses further revealed that treatment of A. awamori degraded B-type condensed tannin (condensed flavan-3-ol via C4–C8 linkage, but exhibited a limited capacity to degrade the condensed tannin containing A-type linkage subunits (C4–C8 coupled C2–O–C7 linkage. These results suggest that the treatment of A. awamori can significantly improve the production of condensed tannin from litchi pericarp.

Physics through the 1990s: Condensed-matter physics

International Nuclear Information System (INIS)

1986-01-01

In this survey of condensed-matter physics we describe the current status of the field, present some of the significant discoveries and developments in it since the early 1970s, and indicate some areas in which we expect that important discoveries will be made in the next decade. We also describe the resources that will be required to produce these discoveries. This volume is organized as follows. The first part is devoted to a discussion of the importance of condensed-matter physics; to brief descriptions of several of the most significant discoveries and advances in condensed-matter physics made in the 1970s and early 1980s, and of areas that appear to provide particularly exciting research opportunities in the next decade; and to a presentation of the support needs of condensed-matter physicists in the next decade and of recommendations aimed at their provision. Next, the subfields of condensed-matter physics are reviewed in detail. The volume concludes with several appendixes in which new materials, new experimental techniques, and the National Facilities are reviewed

Condensers

International Nuclear Information System (INIS)

Andrieux, M.B.

1984-01-01

Characteristics of the condenser cooling waters of various French 900 MW nuclear power plants. Design and description of various types of condensers: condensers feeded directly with river water, condensers feeded by cooling towers, condensers feeded with sea water of brackish water. Presentation of the main problems encountered with the brass bundles (ammoniacal corrosion, erosion of the peripheral tubes, vibrations of the tubes), with the titanium bundles, with the tubular plates, the tubes-tubular plates assemblies, the coatings of the condenser water chamber (sea water), the vapor by-pass and with the air inlet. Analysis of the in service performances such as condensation pressure, oxygen content and availability [fr

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

Condensate induced water hammer in a steam distribution system results in fatality

International Nuclear Information System (INIS)

Debban, H.L.; Eyre, L.E.

1996-02-01

Water hammer event s in steam distribution piping interrupt service and have the potential to cause serious injury and property damage. Conditions of condensation induced water hammer are discussed and recommendations aimed to improve safety of steam systems are presented. Condensate induced water hammer events at Hanford, a DOE facility, are examined

Some concepts in condensed phase chemical kinetics

International Nuclear Information System (INIS)

Adelman, S.A.

1986-01-01

Some concepts in condensed phase chemical kinetics which have emerged from a recent rigorous statistical mechanical treatment of condensed phase chemical reaction dynamics (S.A. Adelman, Adv. Chem. Phys.53:61 (1983)) are discussed in simple physical terms

Accelerators for condensed matter research

International Nuclear Information System (INIS)

Williams, P.R.

1990-01-01

The requirement for high energy, high luminosity beams has stimulated the science and engineering of accelerators to a point where they open up opportunities for new areas of scientific application to benefit from the advances driven by particle physics. One area of great importance is the use of electron or positron storage rings as a source of intense VUV or X-ray synchrotron radiation. An accelerator application that has grown in prominence over the last 10 years has been spallation neutron sources. Neutrons offer an advantage over X-rays as a condensed matter probe because the neutron energy is usually of the same order as the room temperature thermal energy fluctuations in the sample being studied. Another area in which accelerators are playing an increasingly important role in condensed matter research concerns the use of Mu mesons, Muons, as a probe. This paper also presents a description of the ISIS Spallation Neutron Source. The design and status of the facility are described, and examples are given of its application to the study of condensed matter. (N.K.)

Preoperational test report, primary ventilation condenser cooling system

Energy Technology Data Exchange (ETDEWEB)

Clifton, F.T.

1997-10-29

This represents the preoperational test report for the Primary Ventilation Condenser Cooling System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system uses a closed chilled water piping loop to provide offgas effluent cooling for tanks AY101, AY102, AZ1O1, AZ102; the offgas is cooled from a nominal 100 F to 40 F. Resulting condensation removes tritiated vapor from the exhaust stack stream. The piping system includes a package outdoor air-cooled water chiller with parallel redundant circulating pumps; the condenser coil is located inside a shielded ventilation equipment cell. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.

Preoperational test report, primary ventilation condenser cooling system

International Nuclear Information System (INIS)

Clifton, F.T.

1997-01-01

This represents the preoperational test report for the Primary Ventilation Condenser Cooling System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system uses a closed chilled water piping loop to provide offgas effluent cooling for tanks AY101, AY102, AZ1O1, AZ102; the offgas is cooled from a nominal 100 F to 40 F. Resulting condensation removes tritiated vapor from the exhaust stack stream. The piping system includes a package outdoor air-cooled water chiller with parallel redundant circulating pumps; the condenser coil is located inside a shielded ventilation equipment cell. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System

Addressing social aspects associated with wastewater treatment facilities

International Nuclear Information System (INIS)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia

2016-01-01

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

Addressing social aspects associated with wastewater treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia, E-mail: lguerecah@iingen.unam.mx

2016-02-15

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

An easily implemented static condensation method for structural sensitivity analysis

Science.gov (United States)

Gangadharan, S. N.; Haftka, R. T.; Nikolaidis, E.

1990-01-01

A black-box approach to static condensation for sensitivity analysis is presented with illustrative examples of a cube and a car structure. The sensitivity of the structural response with respect to joint stiffness parameter is calculated using the direct method, forward-difference, and central-difference schemes. The efficiency of the various methods for identifying joint stiffness parameters from measured static deflections of these structures is compared. The results indicate that the use of static condensation can reduce computation times significantly and the black-box approach is only slightly less efficient than the standard implementation of static condensation. The ease of implementation of the black-box approach recommends it for use with general-purpose finite element codes that do not have a built-in facility for static condensation.

Condensation pool experiments with steam using DN200 blowdown pipe

International Nuclear Information System (INIS)

Laine, J.; Puustinen, M.

2005-08-01

This report summarizes the results of the condensation pool experiments with steam using a DN200 blowdown pipe. Altogether five experiment series, each consisting of several steam blows, were carried out in December 2004 with a scaled-down test facility designed and constructed at Lappeenranta University of Technology. The main purpose of the experiments was to increase the understanding of different phenomena in the condensation pool during steam discharge. (au)

Phase 1 Testing Results of Immobilization of WTP Effluent Management Facility Evaporator Bottoms Core Simulant

Energy Technology Data Exchange (ETDEWEB)

Cozzi, Alex D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-01-05

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream during full WTP operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility. However, during the Direct Feed LAW (DFLAW) scenario, planned disposition of this stream is to evaporate it in a new evaporator in the Effluent Management Facility (EMF) and then return it to the LAW melter. It is important to understand the composition of the effluents from the melter and new evaporator so that the disposition of these streams can be accurately planned and accommodated. Furthermore, alternate disposition of this stream would eliminate recycling of problematic components, and would enable less integrated operation of the LAW melter and the Pretreatment Facilities. Alternate disposition would also eliminate this stream from recycling within WTP when it begins operations and would decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Melter Off-Gas Condensate stream will contain components that are volatile at melter temperatures and are problematic for the glass waste form, such as halides and sulfate, along with entrained, volatile, and semi-volatile metals, such as Hg, As, and Se. Because this stream will recycle within WTP, these components accumulate in the Melter Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Diverting the stream reduces the halides and sulfate that get recycled to the melter, and is a key objective of this work. This overall program examines the potential treatment and immobilization of this stream to enable alternative disposal. The objective of earlier tasks was to formulate and prepare a

Wireless local network architecture for Naval medical treatment facilities

OpenAIRE

Deason, Russell C.

2004-01-01

Approved for public release; distribution is unlimited In today's Navy Medicine, an approach towards wireless networks is coming into view. The idea of developing and deploying workable Wireless Local Area Networks (WLAN) throughout Naval hospitals is but just a few years down the road. Currently Naval Medical Treatment Facilities (MTF) are using wired Local Area Networks (LANs) throughout the infrastructure of each facility. Civilian hospitals and other medical treatment facilities have b...

242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

International Nuclear Information System (INIS)

Von Bargen, B.H.

1994-01-01

The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF)

242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

Energy Technology Data Exchange (ETDEWEB)

Von Bargen, B.H.

1994-09-29

The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF).

3718-F Alkali Metal Treatment and Storage Facility Closure Plan

International Nuclear Information System (INIS)

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed

RETROFITTING CONTROL FACILITIES FOR WET-WEATHER FLOW TREATMENT

Science.gov (United States)

Available technologies were evaluated to demonstrate the technical feasibility and cost effectiveness of retrofitting existing facilities to handle wet-weather flow. Cost/benefit relationships were also compared to construction of new conventional control and treatment facilities...

Nuclear power generation facility

International Nuclear Information System (INIS)

Kubo, Mitsuji.

1996-01-01

Main steams are introduced from a moisture separation device for removing moisture content of the main steams to a low pressure turbine passing through a cross-around pipe. A condensate desalter comprising a mixed floor-type desalting tower using granular ion exchange resins is disposed at the downstream of the main condensator by way of condensate pipelines, and a feedwater heater is disposed at the downstream. Structural members of the main condensator are formed by weather proof steels. Low alloy steels are used partially or entirely for the cross-around pipe, gas extraction pipelines, heat draining pipelines, inner structural members other than pipelines in the feedwater heater, and the body and the inner structural members of the moisture separator. Titanium or a titanium alloy is used for the pipelines in the main condensator. With such a constitution, BWR type reactor facilities, in which the concentration of cruds inflown to the condensate cleanup system is reduced to simplify the condensate cleanup device can be obtained. (I.N.)

Improvement of Oil-Vapor Treatment Facility for Wolsong Unit 3,4

International Nuclear Information System (INIS)

Kim, Jeong Guk; Kwon, S. W.; Lee, H. S.

2009-11-01

With the purpose to minimize an oil-vapor discharge to the atmosphere and to be an environmentally friendly nuclear power plant by an improvement of mist eliminator for turbine lubricant system at Wolsong Nuclear Power Plant Unit 3,4, this project - project name : Improvement of Oil-vapor Treatment Facility for Wolsong Unit 3,4 - was conducted for six months (from Apr. 15, 2009 to Oct. 14, 2009). This Project contains Oil-vapor Source and Environmental Regulation, Analysis on the Present Oil-vapor Treatment Facility, Improvement of Oil-vapor Treatment Facility, Test Facility Design, Fabrication, Installation, Test Operation, Evaluation of the Facility

Cloud Condensation Nuclei Particle Counter (CCN) Instrument Handbook

Energy Technology Data Exchange (ETDEWEB)

Uin, Janek [Brookhaven National Lab. (BNL), Upton, NY (United States)

2016-04-01

The Cloud Condensation Nuclei Counter—CCN (Figure 1) is a U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility instrument for measuring the concentration of aerosol particles that can act as cloud condensation nuclei [1, 2]. The CCN draws the sample aerosol through a column with thermodynamically unstable supersaturated water vapor that can condense onto aerosol particles. Particles that are activated, i.e., grown larger in this process, are counted (and sized) by an Optical Particle Counter (OPC). Thus, activated ambient aerosol particle number concentration as a function of supersaturation is measured. Models CCN-100 and CCN-200 differ only in the number of humidifier columns and related subsystems: CCN-100 has one column and CCN-200 has two columns along with dual flow systems and electronics.

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

International Nuclear Information System (INIS)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

The Wastewater Treatment Test Facility at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Richardson, S.A.; Kent, T.E.; Taylor, P.A.

1995-01-01

The Wastewater Treatment Test Facility (WTTF) contains 0.5 L/min test systems which provide a wide range of physical and chemical separation unit operations. The facility is a modified 48 foot trailer which contains all the unit operations of the ORNL's Process Waste Treatment Plant and Nonradiological Wastewater Treatment Plant including chemical precipitation, clarification, filtration, ion-exchange, air stripping, activated carbon adsorption, and zeolite system. This facility has been used to assess treatability of potential new wastewaters containing mixed radioactive, hazardous organic, and heavy metal compounds. With the ability to simulate both present and future ORNL wastewater treatment systems, the WTTF has fast become a valuable tool in solving wastewater treatment problems at the Oak Ridge reservation

Energy Efficiency Strategies for Municipal Wastewater Treatment Facilities

Energy Technology Data Exchange (ETDEWEB)

Daw, J.; Hallett, K.; DeWolfe, J.; Venner, I.

2012-01-01

Water and wastewater systems are significant energy consumers with an estimated 3%-4% of total U.S. electricity consumption used for the movement and treatment of water and wastewater. Water-energy issues are of growing importance in the context of water shortages, higher energy and material costs, and a changing climate. In this economic environment, it is in the best interest for utilities to find efficiencies, both in water and energy use. Performing energy audits at water and wastewater treatment facilities is one way community energy managers can identify opportunities to save money, energy, and water. In this paper the importance of energy use in wastewater facilities is illustrated by a case study of a process energy audit performed for Crested Butte, Colorado's wastewater treatment plant. The energy audit identified opportunities for significant energy savings by looking at power intensive unit processes such as influent pumping, aeration, ultraviolet disinfection, and solids handling. This case study presents best practices that can be readily adopted by facility managers in their pursuit of energy and financial savings in water and wastewater treatment. This paper is intended to improve community energy managers understanding of the role that the water and wastewater sector plays in a community's total energy consumption. The energy efficiency strategies described provide information on energy savings opportunities, which can be used as a basis for discussing energy management goals with water and wastewater treatment facility managers.

Condensation of steam in horizontal pipes: model development and validation

International Nuclear Information System (INIS)

Szijarto, R.

2015-01-01

This thesis submitted to the Swiss Federal Institute of Technology ETH in Zurich presents the development and validation of a model for the condensation of steam in horizontal pipes. Condensation models were introduced and developed particularly for the application in the emergency cooling system of a Gen-III+ boiling water reactor. Such an emergency cooling system consists of slightly inclined horizontal pipes, which are immersed in a cold water tank. The pipes are connected to the reactor pressure vessel. They are responsible for a fast depressurization of the reactor core in the case of accident. Condensation in horizontal pipes was investigated with both one-dimensional system codes (RELAP5) and three-dimensional computational fluid dynamics software (ANSYS FLUENT). The performance of the RELAP5 code was not sufficient for transient condensation processes. Therefore, a mechanistic model was developed and implemented. Four models were tested on the LAOKOON facility, which analysed direct contact condensation in a horizontal duct

Region 9 NPDES Facilities 2012- Waste Water Treatment Plants

Science.gov (United States)

Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

Theory of decoherence in Bose-Einstein condensate interferometry

Energy Technology Data Exchange (ETDEWEB)

Dalton, B J [ARC Centre for Quantum-Atom Optics and Centre for Atom Optics and Ultrafast Spectroscopy, Swinburne University of Technology, Melbourne, Victoria 3122 (Australia)

2007-05-15

A full treatment of decoherence and dephasing effects in BEC interferometry has been developed based on using quantum correlation functions for treating interferometric effects. The BEC is described via a phase space distribution functional of the Wigner type for the condensate modes and the positive P type for the non-condensate modes. Ito equations for stochastic condensate and non-condensate field functions replace the functional Fokker-Planck equation for the distribution functional and stochastic averages of field function products determine the quantum correlation functions.

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

Characterizing experiments of the PPOOLEX test facility

Energy Technology Data Exchange (ETDEWEB)

Puustinen, M.; Laine, J. (Lappeenranta Univ. of Technology, Nuclear Safety Research Unit (Finland))

2008-07-15

This report summarizes the results of the characterizing test series in 2007 with the scaled down PPOOLEX facility designed and constructed at Lappeenranta University of Technology. Air and steam/air mixture was blown into the dry well compartment and from there through a DN200 blowdown pipe to the condensation pool (wet well). Altogether eight air and four steam/air mixture experiments, each consisting of several blows (tests), were carried out. The main purpose of the experiment series was to study the general behavior of the facility and the performance of basic instrumentation. Proper operation of automation, control and safety systems was also tested. The test facility is a closed stainless steel vessel divided into two compartments, dry well and wet well. The facility is equipped with high frequency measurements for capturing different aspects of the investigated phenomena. The general behavior of the PPOOLEX facility differs significantly from that of the previous POOLEX facility because of the closed two-compartment structure of the test vessel. Heat-up by several tens of degrees due to compression in both compartments was the most obvious evidence of this. Temperatures also stratified. Condensation oscillations and chugging phenomenon were encountered in those tests where the fraction of non-condensables had time to decrease significantly. A radical change from smooth condensation behavior to oscillating one occurred quite abruptly when the air fraction of the blowdown pipe flow dropped close to zero. The experiments again demonstrated the strong diminishing effect that noncondensable gases have on dynamic unsteady loadings experienced by submerged pool structures. BWR containment like behavior related to the beginning of a postulated steam line break accident was observed in the PPOOLEX test facility during the steam/air mixture experiments. The most important task of the research project, to produce experimental data for code simulation purposes, can be

Outline of a fuel treatment facility in NUCEF

International Nuclear Information System (INIS)

Sugikawa, Susumu; Umeda, Miki; Kokusen, Junya

1997-03-01

This report presents outline of the nuclear fuel treatment facility for the purpose of preparing solution fuel used in Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF), including descriptions of process conditions and dimensions of major process equipments on dissolution system of oxide fuel, chemical adjustment system, purification system, acid recovery system, solution fuel storage system, and descriptions of safety design philosophy such as safety considerations of criticality, solvent fire, explosion of hydrogen and red-oil and so on. (author)

Three-dimensional studies of mixing and stratification in containments cooled by internal condensers

Energy Technology Data Exchange (ETDEWEB)

Putz, F.; Dury, T. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

2001-07-01

Within the scope of the fourth EU Framework Programme IPSS project, two passive containment cooling systems, the so-called Building Condenser (BC, under an additional bilateral contract between PSI and Siemens) and Plate Condenser (PC), have been studied at the PSI PANDA facility. From the two tests series, tests BC4 and PC1 have been selected for analysis with the code GOTHIC 6.0. Particular phenomena which are of importance with regard to the condensers operating conditions (mixing/stratification of non-condensable gases, such as air and helium) have been analysed. The GOTHIC simulations have been complemented by CFD calculations with CFX-4. (author)

Three-dimensional studies of mixing and stratification in containments cooled by internal condensers

International Nuclear Information System (INIS)

Putz, F.; Dury, T.

2001-01-01

Within the scope of the fourth EU Framework Programme IPSS project, two passive containment cooling systems, the so-called Building Condenser (BC, under an additional bilateral contract between PSI and Siemens) and Plate Condenser (PC), have been studied at the PSI PANDA facility. From the two tests series, tests BC4 and PC1 have been selected for analysis with the code GOTHIC 6.0. Particular phenomena which are of importance with regard to the condensers operating conditions (mixing/stratification of non-condensable gases, such as air and helium) have been analysed. The GOTHIC simulations have been complemented by CFD calculations with CFX-4. (author)

Argonne-West facility requirements for a radioactive waste treatment demonstration

International Nuclear Information System (INIS)

Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

1995-01-01

At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

Bubbler condenser related research work. Present situation

International Nuclear Information System (INIS)

2001-02-01

Intensive discussions within the OECD Support Group on 'VVER-440 Bubbler Condenser Containment Research Work' between 1991 and 1994 demonstrated the need for supplementary research work to achieve an adequate level of basic knowledge. In 1994, the European Commission (EC) asked for a specific 'VVER-440/213 Bubble Condenser Qualification Feasibility Study', which was finished early in 1996, confirming the need for additional research in this field. The Feasibility study formed the basis for the Bubble Condenser Experimental Qualification Project (BCEQ) with two separate experimental activities to be executed within the frame of the PHARE/TACIS 2.13/95 project of the European Commission. A first activity served to study the thermal-hydraulic phenomena and the associated structure dynamic interactions. This part of the project was performed at EREC, in Elektrogorsk, Russia. The design of the test facility was based on the prototypical bubbler condenser configuration for the Hungarian Paks nuclear power plant. A second activity addressed the structural integrity of certain components of the bubbler condenser steel structures under DBA-typical conditions. This part of the project was performed at VUEZ, in Levice, Slovak Republic. The design of the components of this facility was based on the structural properties of the Dukovany and/or Bohunice nuclear power plants. A third component of the BCEQ project was specified later asking for analytical studies, which should be supported by a number of small-scale separate effects tests to be performed at SVUSS, in Bechovice, Czech Republic. The main experimental and analytical results of the BCEQ test campaigns have been presented and discussed within the frame of the 4. meeting of the Technical Advisory Committee to the BCEQ (Bubble Condenser Experimental Qualification) Project in Brussels in December 1999 and on occasion of the 11. OECD Support Group Meeting in Berlin in April 2000. The discussions had evidenced several

Opportunities for Automated Demand Response in California Wastewater Treatment Facilities

Energy Technology Data Exchange (ETDEWEB)

Aghajanzadeh, Arian [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Wray, Craig [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); McKane, Aimee [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2015-08-30

Previous research over a period of six years has identified wastewater treatment facilities as good candidates for demand response (DR), automated demand response (Auto-­DR), and Energy Efficiency (EE) measures. This report summarizes that work, including the characteristics of wastewater treatment facilities, the nature of the wastewater stream, energy used and demand, as well as details of the wastewater treatment process. It also discusses control systems and automated demand response opportunities. Furthermore, this report summarizes the DR potential of three wastewater treatment facilities. In particular, Lawrence Berkeley National Laboratory (LBNL) has collected data at these facilities from control systems, submetered process equipment, utility electricity demand records, and governmental weather stations. The collected data were then used to generate a summary of wastewater power demand, factors affecting that demand, and demand response capabilities. These case studies show that facilities that have implemented energy efficiency measures and that have centralized control systems are well suited to shed or shift electrical loads in response to financial incentives, utility bill savings, and/or opportunities to enhance reliability of service. In summary, municipal wastewater treatment energy demand in California is large, and energy-­intensive equipment offers significant potential for automated demand response. In particular, large load reductions were achieved by targeting effluent pumps and centrifuges. One of the limiting factors to implementing demand response is the reaction of effluent turbidity to reduced aeration at an earlier stage of the process. Another limiting factor is that cogeneration capabilities of municipal facilities, including existing power purchase agreements and utility receptiveness to purchasing electricity from cogeneration facilities, limit a facility’s potential to participate in other DR activities.

findings from audits of specialist treatment facilities

African Journals Online (AJOL)

Adele

population groups in terms of the allocation of resources to, and the quality of ... facilities has decreased in real terms, limiting their treatment capacity and their capacity ... fordable, and accessible substance abuse treatment services1, ... The terms “white, black, asian/indian, and coloured” refer to demographic markers and ...

Paul Scherrer Institute Scientific Report 1998. Volume III: Condensed Matter Research with Neutrons

International Nuclear Information System (INIS)

Schefer, Juerg; Castellazzi, Denise; Bucher-Zimmermann, Claudia

1999-01-01

As a consequence of a major reorganisation at PSI, a new department has been formed with the groups focussing on research of condensed matter. The activities of the Laboratory of Neutron Scattering (jointly operated with the Swiss Federal Institute of Technology, ETH Zuerich), the Condensed Matter Theory Group, and the Group for Low Temperature Facilities, are described in this annual report

Proton facility economics: the importance of "simple" treatments.

Science.gov (United States)

Johnstone, Peter A S; Kerstiens, John; Richard, Helsper

2012-08-01

Given the cost and debt incurred to build a modern proton facility, impetus exists to minimize treatment of patients with complex setups because of their slower throughput. The aim of this study was to determine how many "simple" cases are necessary given different patient loads simply to recoup construction costs and debt service, without beginning to cover salaries, utilities, beam costs, and so on. Simple cases are ones that can be performed quickly because of an easy setup for the patient or because the patient is to receive treatment to just one or two fields. A "standard" construction cost and debt for 1, 3, and 4 gantry facilities were calculated from public documents of facilities built in the United States, with 100% of the construction funded through standard 15-year financing at 5% interest. Clinical best case (that each room was completely scheduled with patients over a 14-hour workday) was assumed, and a statistical analysis was modeled with debt, case mix, and payer mix moving independently. Treatment times and reimbursement data from the investigators' facility for varying complexities of patients were extrapolated for varying numbers treated daily. Revenue assumptions of $X per treatment were assumed both for pediatric cases (a mix of Medicaid and private payer) and state Medicare simple case rates. Private payer reimbursement averages $1.75X per treatment. The number of simple patients required daily to cover construction and debt service costs was then derived. A single gantry treating only complex or pediatric patients would need to apply 85% of its treatment slots simply to service debt. However, that same room could cover its debt treating 4 hours of simple patients, thus opening more slots for complex and pediatric patients. A 3-gantry facility treating only complex and pediatric cases would not have enough treatment slots to recoup construction and debt service costs at all. For a 4-gantry center, focusing on complex and pediatric cases alone

Development of analytical model for condensation of vapor mixture of nitric acid and water affected volatilized ruthenium behavior in accident of evaporation to dryness by boiling of reprocessed high level liquid waste at fuel reprocessing facilities

International Nuclear Information System (INIS)

Yoshida, Kazuo

2016-08-01

An accident of evaporation to dryness by boiling of high level liquid waste is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, continuous vaporing of nitric acid and water leads to increase Ru volatilization in liquid waste temperature over 120degC at later boiling and dry out phases. It has been observed at the experiments with actual and synthetic liquid waste that some amount of Ru volatilizes and transfers into condensed nitric acid solution at those phases. The nitric acid and water vapor flowing from waste tank are expected to condense at compartments of actual facilities building. The volatilized Ru could transfer into condensed liquid. It is key issues for quantifying the amount of transferred Ru through the facility building to simulate these thermodynamic and chemical behaviors. An analytical model has been proposed in this report based on the condensation mechanisms of nitric acid and water in vapor-liquid equilibria. It has been also carried out for the proposed model being feasible to formulate the activity coefficients and to review the thermodynamic properties of nitric acid solution. Practicability of the proposed analytical model has been shown successfully through the feasibility study with simulation of an experiment result. (author)

Basic design of the test facility for the two-phase critical flow with non-condensable gas

International Nuclear Information System (INIS)

Chang, Seok Kyu; Kim, Chang Hwe; Chung, Chang Hwan

2000-12-01

The two-phase critical flow test with non-condensible gas is for the simulation of the critical flow phenomena which can be occurred during SB-LOCA on SMART reactor. The basic design of the test facility for the actual installation is performed from the basis of the previous conceptual design according to the test requirements. The 1.3m 3 pressure vessel has the circulation pipeline which contains pump(5m 3 /hr), main heater(150KW) and cooler for heating the working fluid to the test temperature within 6 hours. The N2 gas, water supply line are attached to the upper part and test section, flowmeter and various sensors are installed at the lower part of the pressure vessel. The suppression tank is for the storage and cooling of the discharged water. The N2 gas storage tank provides the system pressure to the pressure vessel during the test. The 0.7m 3 N2 gas injection tank supplies the required N2 gas to the entrance of the test section. Since these N2 supply systems require much amount of gas during short period, multistage valve systems and optimal control logics are needed and applied. For the filling of the N2 gas to the N2 storage tank, 5m 3 LN2 tank and related gas converting system were designed. The operating mode of the test facility can be classified to the starting, steady, main test and cooling modes and the proper monitoring and control logics are developed for each operating mode. The operation of the test facility is performed through the PLC and the acquisition of the test data is done with DAS

Hazardous Waste Treatment Facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1994-01-01

To centralize treatment, storage, and areas for hazardous wastes, Los Alamos National Laboratory has designed a 1115 m2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes, radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks; bulking small organic waste volumes; processing scintillation vials; treating reactives such as lithium hydride and pyrophoric uranium; treating contaminated solids such as barium sand; treating plating wastes and other solutions with heavy metals and oxidizing organics: Separate treatment rooms will allow workers to avoid mixing waste types and prevent cross-contamination. The ventilation air from the treatment areas may contain hazardous or radioactive dust. Gas may also leak from process equipment. The gas treatment process includes separating solids and gases and neutralization or adsorption of the hazardous gases. The ventilation air from each room will first be filtered before being scrubbed in a common gas caustic scrubber on an outside pad. There are two levels of exhaust in each treatment room, one for heavy gases and another for light gases. Several features help mitigate or eliminate hazards due to spills and releases: each treatment room is sealed and under slight negative pressure; each room has its own HEPA filtration; to avoid mixing of incompatible wastes and reagents, portable individual spill-containment trays are used for skids, to limit the danger of spills, the waste is directly transferred from outside storage to the treatment room; to mitigate the consequences of a gas release in the room, mobile hoods are connected to the exhaust-air treatment system; the floor, walls, ceilings, fixtures, ducts, and piping are made of acid-resistant material or are coated

A Preliminary Study of Transverse Curvature Effects on Condensation Heat Transfer on Vertical Tube in the Presence of Non-condensable Gas

Energy Technology Data Exchange (ETDEWEB)

Lee, Yeon Gun; Kim, Sin [Jeju National Univ., Jeju (Korea, Republic of); Jerng, Dong Wook [Chung Ang Univ., Seoul (Korea, Republic of)

2013-10-15

In this study, the effect of the transverse curvature on the condensation HTC on a vertical tube in the presence of air is preliminarily investigated by using the analysis of boundary layer for free convective heat transfer. The results indicate that the heat transfer performance can be enhanced as the outer diameter of condenser tubes is small. To confirm this curvature effect, an experimental program to obtain the condensation heat transfer data for various values of tube diameter is indispensable. Currently, by a joint research project of Jeju National University and Chung-Ang University, a condensation test facility is being designed and constructed to acquire the condensation HTC data as shown in Fig. 3. From a series of experiment on a single vertical tube, the effects of not only the tube diameter but the inclination, the existence of fins and the local velocity of a bulk mixture by natural circulation will be evaluated precisely. An empirical correlation for the condensation heat transfer of a steam-air mixture will also be developed for design optimization and performance evaluation of the PCCS. The Passive Containment Cooling System (PCCS) provides passive means to remove the decay heat and protect the integrity of the containment during severe accidents. Korea, in which all the NPPs employ the concrete containment, may adopt a PCCS using internal condensers. In the event of the loss-of-coolant accident (LOCA), steam released from the reactor coolant system is mixed with air inside the containment and condensed on the outer surface of inclined condenser tubes. It is noted that, among previous theoretical and empirical models for condensation on outer wall in the presence of non-condensable gas, no one took into account the effect of a tube diameter. Though the condensation heat transfer coefficient may vary with transverse curvature of condenser tubes, such a curvature effect has not been reported so far. In this study, a preliminary analysis is conducted

A Preliminary Study of Transverse Curvature Effects on Condensation Heat Transfer on Vertical Tube in the Presence of Non-condensable Gas

International Nuclear Information System (INIS)

Lee, Yeon Gun; Kim, Sin; Jerng, Dong Wook

2013-01-01

In this study, the effect of the transverse curvature on the condensation HTC on a vertical tube in the presence of air is preliminarily investigated by using the analysis of boundary layer for free convective heat transfer. The results indicate that the heat transfer performance can be enhanced as the outer diameter of condenser tubes is small. To confirm this curvature effect, an experimental program to obtain the condensation heat transfer data for various values of tube diameter is indispensable. Currently, by a joint research project of Jeju National University and Chung-Ang University, a condensation test facility is being designed and constructed to acquire the condensation HTC data as shown in Fig. 3. From a series of experiment on a single vertical tube, the effects of not only the tube diameter but the inclination, the existence of fins and the local velocity of a bulk mixture by natural circulation will be evaluated precisely. An empirical correlation for the condensation heat transfer of a steam-air mixture will also be developed for design optimization and performance evaluation of the PCCS. The Passive Containment Cooling System (PCCS) provides passive means to remove the decay heat and protect the integrity of the containment during severe accidents. Korea, in which all the NPPs employ the concrete containment, may adopt a PCCS using internal condensers. In the event of the loss-of-coolant accident (LOCA), steam released from the reactor coolant system is mixed with air inside the containment and condensed on the outer surface of inclined condenser tubes. It is noted that, among previous theoretical and empirical models for condensation on outer wall in the presence of non-condensable gas, no one took into account the effect of a tube diameter. Though the condensation heat transfer coefficient may vary with transverse curvature of condenser tubes, such a curvature effect has not been reported so far. In this study, a preliminary analysis is conducted

Experimental study of steam condensation regime map for simplified spargers

International Nuclear Information System (INIS)

Kim, Y. S.; Yoon, Y. J.; Song, C. H.; Park, C. K.; Kang, H. S.; Jun, H. K.

2003-01-01

An experimental study was conducted to produce a condensation regime map for single-hole and 4-hole steam spargers using GIRLS facility. The regime map for a single-hole sparger was derived using parameters such as the frequency and magnitude of the dynamic pressure. For 4-hole sparager, the regime map was derived using the trends of sound and dynamic pressure. Using the single-hole and 4-hole data, a steam jet condensation regime map was suggested with respect to pool temperature and steam mass flux

First Dutch Consensus of Pain Quality Indicators for Pain Treatment Facilities.

Science.gov (United States)

de Meij, Nelleke; van Grotel, Marloes; Patijn, Jacob; van der Weijden, Trudy; van Kleef, Maarten

2016-01-01

There is a general consensus about the need to define and improve the quality of pain treatment facilities. Although guidelines and recommendations to improve the quality of pain practice management have been launched, provision of appropriate pain treatment is inconsistent and the quality of facilities varies widely. The aim of the study was to develop an expert-agreed list of quality indicators applicable to pain treatment facilities. The list was also intended to be used as the basis for a set of criteria for registered status of pain treatment facilities. The University Pain Center Maastricht at the Department of Anesthesiology and Pain Management of the Maastricht University Medical Center conducted a 3-round Delphi study in collaboration with the Board of the Pain Section of the Dutch Society of Anesthesiologists (NVA). Twenty-five quality indicators were selected as relevant to 2 types of pain treatment facilities, pain clinics and pain centers. The final expert-agreed list consisted of 22 quality indicators covering 7 quality domains: supervision, availability of care, staffing level and patient load, quality policy, multidisciplinarity, regionalization, and research and education. This set of quality indicators may facilitate organizational evaluation and improve insight into service quality from the perspectives of patients, pain specialists, and other healthcare professionals. Recommendations for improvements to the current set of quality indicators are made. In 2014 the process of registering pain treatment facilities in the Netherlands started; facilities can register as a pain clinic or pain center. © 2015 World Institute of Pain.

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental ampersand Regulatory Planning ampersand Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria

UTILIZATION OF AQUEOUS-TAR CONDENSATES FORMED DURING GASIFICATION

Directory of Open Access Journals (Sweden)

Anna Kwiecińska

2016-11-01

Full Text Available Gasification of solid fuels is an alternative process for energy production using conventional and renewable fuels. Apart from desired compounds, i.e. carbon oxide, hydrogen and methane, the produced gas contains complex organic (tars and inorganic (carbonizate, ammonia contaminants. Those substances, together with water vapor, condensate during cooling of the process gas, what results in the formation of aqueous-tar condensate, which requires proper methods of utilization. The management of this stream is crucial for commercialization and application of the gasification technology. In the paper the treatment of aqueous-tar condensates formed during biomass gasification process is discussed. The removal of tars from the stream was based on their spontaneous separation. The aqueous stream was subjected to ultrafiltration operated at different pressures. Such a treatment configuration enabled to obtain highly concentrated retentate, which could be recycled to the gasifier, and filtrate, which could be subjected to further treatment.

Experimental investigation of condensation and mixing during venting of a steam / non-condensable gas mixture into a pressure suppression pool

Energy Technology Data Exchange (ETDEWEB)

De Walsche, C.; Cachard, F. de

2000-07-01

Experiments have been performed in the LINX facility to investigate condensation and mixing phenomena in pressure Suppression Pools (SPs), in the context of the European Simplified Boiling Water Reactor (ESBWR) study. As a contribution to the TEPSS project of the 4th European Framework Programme, eight medium-scale, separate-effect tests were carried out in which constant steam/air flow rates were injected below the surface of a two-metre diameter water pool, maintained at constant pressure, through a large downward vent. The vessel pressure was regulated, the pool temperature rising until equilibrium conditions with the incoming gas were reached. The SP temperature distribution was measured, as well as the inlet and outlet gas flow rates, and the overall condensation rate was estimated using mass and heat balances. The test matrix was based on steam mass floret and air mass fraction of the injected gas, the vent immersion depth, and the vessel pressure. Overall, the condensation was shown to be efficient for all tests performed, even for high non-condensable gas concentrations of the injected gas. Thermal stratification above the vent outlet was shown to be moderate. The tests performed allowed a better understanding to be gained of the mechanisms of condensation and mixing in the SP and Wetwell, and results were incorporated into an ORACLE database, to be used for further model development. (authors)

A comprehensive centralized control system for radiation waste treatment facility

International Nuclear Information System (INIS)

Kong Jinsong

2014-01-01

A comprehensive centralized control system is designed for the radiation waste treatment facility that lacking of coordinated operational mechanism for the radiation waste treatment. The centralized control and alarm linkage of various systems is implemented to ensure effectively the safety of nuclear facility and materials, improve the integral control ability through advanced informatization ways. (author)

Determination of Reasons of Obstruction in the Condensate Stabilizer System of Namconson Gas Treatment Terminal by Radioisotope Techniques

International Nuclear Information System (INIS)

Bui Quang Tri; Nguyen Huu Quang; Dang Nguyen The Duy; Tran Tri Hai; Tran Thanh Minh

2008-01-01

The Condensate Stabilizer System of Namconson Gas Treatment Terminal was designed with operational flow rate of 60 m 3 /h but for unknown reason it ran efficiently below 20 m 3 /h. The Radiotracer in combination with Gamma Scan was used to investigate in understanding the reasons. The results showed the build up at the bottom of Trap out Tray which caused obstruction of condensate flow in the outlet of Trap out Tray. As a results the feed flow rate to Reboiler from Trap out Tray lowered into 1/3 and the remaining 2/3 by passing the Reboiler by overflow to the Sump. (author)

Paul Scherrer Institute Scientific Report 1998. Volume III: Condensed Matter Research with Neutrons

Energy Technology Data Exchange (ETDEWEB)

Schefer, Juerg; Castellazzi, Denise; Bucher-Zimmermann, Claudia [eds.

1999-09-01

As a consequence of a major reorganisation at PSI, a new department has been formed with the groups focussing on research of condensed matter. The activities of the Laboratory of Neutron Scattering (jointly operated with the Swiss Federal Institute of Technology, ETH Zuerich), the Condensed Matter Theory Group, and the Group for Low Temperature Facilities, are described in this annual report figs., tabs., refs.

Patient Satisfaction in Military Dental Treatment Facilities

Science.gov (United States)

2006-03-07

the variance in regards to overall satisfaction. 15. SUBJECT TERMS Dentistry, Patient Satisfaction, Military, Consumer Satisfaction, Dental... patient satisfaction in military dental treatment facilities. Dental health is extremely important for the military as dental assets are not always... customer satisfaction is an important component of military dental care. Quarterly patient satisfaction reports are generated for each dental treatment

Training manual for process operation and management of radioactive waste treatment facility

Energy Technology Data Exchange (ETDEWEB)

Shon, J. S.; Kim, K. J.; Ahn, S. J. [and others

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure.

Training manual for process operation and management of radioactive waste treatment facility

International Nuclear Information System (INIS)

Shon, J. S.; Kim, K. J.; Ahn, S. J.

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure

Treatment of wastes from a central spent-fuel rod consolidation facility

International Nuclear Information System (INIS)

Ross, W.A.

1986-01-01

The consolidation of commercial spent-fuel rods at a central treatment facility (such as the proposed Monitored Retrievable Storage Facility) will generate several types of waste, which may require treatment and disposal. Eight alternatives for the treatment of the wastes have been evaluated as part of DOE's Nuclear Waste Treatment Program at the Pacific Northwest Laboratory. The evaluation considered the system costs, potential waste form requirements, and processing characteristics

Analytical study of condensation heat transfer on titanium tube with super-hydrophobic surface

Energy Technology Data Exchange (ETDEWEB)

Ji, Dae Yun; Park, Hyun Gyu; Lee, Kwon Yeong [Handong Global University, Pohang (Korea, Republic of)

2016-05-15

There are many nuclear or fossil power plants which occupy more than 85% among entire power plants in the world. These plants release heat through condenser into nature. The condenser is an important component for cooling the working fluid after the turbine. Its performance is related with material and size of its tubes. To have good performance or to reduce condenser size, it is important to increase condensation heat transfer coefficient on condenser tubes. Ma et al. executed heat transfer experiment in dropwise condensation with non-condensable gas, and studied how the amount of air and pressure difference affect condensation heat transfer coefficient. The more non-condensable gas existed, the condensation heat transfer coefficient was decreased. Shen et al. studied condensation heat transfer at horizontal bundle tubes. Several variables such as coolant velocity, saturated pressure, and surface conditions were studied. As a result, surface modified brass tube and stainless tube showed higher condensation heat transfer coefficient as much as 1.3 and 1.4 times comparing with their bare tubes, in 70 kPa vacuum condition respectively. Rausch et al. studied dropwise condensation on ion-implanted titanium surface. Experimental study is performed to evaluate the performance of surface modified titanium tube in vacuum state. SAM coating is used to make super-hydrophobic surface of titanium tube. Preliminary analysis were performed considering filmwise and dropwise condensations, respectively. Experiment facility is almost prepared and the test result will be shown soon.

The once-through mode of steam generator reflux condensation in loss of coolant accident scenarios

International Nuclear Information System (INIS)

Liao, Y.; Guentay, S.; Suckow, D.

2009-01-01

The once-through mode of steam generator reflux condensation in the presence of noncondensable gases and/or aerosols for LOCA scenarios is introduced. This phenomenon is planned to be investigated at Paul Scherrer Institute in the ARTIST/RFLX experimental program. The plausible accident scenarios associated with the once-through reflux condensation are analyzed with MELCOR to study the safety significance and the boundary conditions of this phenomenon. This work presents the recent PSI experimental and analytical work on reflux condensation: the progress of modification to the ARTIST test facility for the purpose to study reflux condensation, and the analytical model for the once-through reflux condensation in the presence of noncondensable gas using the heat and mass transfer analogy approach. Future experimental and analytical work on reflux condensation is also outlined. (author)

Centralized treatment facility for L/ILW produced in Iran

International Nuclear Information System (INIS)

Ettehadian, M.; Momenzadeh, S.; Ansar, M.; Burcl, R.

2001-01-01

Full text: Normal operation of 5 MW research reactor, and radioisotope application in medicine, industry and research institutes generate a significant amount of low level radioactive waste. The volume is expected to increase with the expansion of nuclear application. This paper describes the establishing of centralized waste treatment facility developed by Atomic Energy Organization of Iran (AEOI) using IAEA technical assistance and recommendation. The new treatment facility will enable the currently produced RW to be treated conditioned and stored until a national repository becomes available. The centralized facility consists of a waste processing and storage buildings, which will be used to store conditioned waste drums. The treatment methods used for liquid wastes are precipitation, ion exchange and ultra filtration followed by In-drum cementation of residues. An In-drum compactor will be used for compaction of solid wastes. Safe management of low and intermediate radioactive waste, better protection of environment and population and applying suitable and economical processes for treatment of L/ILW are the other objectives of this activity. (author)

Acceptance test procedure for C-018H, 242-A evaporator/PUREX plant process condensate treatment facility

International Nuclear Information System (INIS)

Parrish, D.E.

1994-01-01

This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Electrical/Instrumentation system function as required for this facility. Each company or organization participating in this ATP will designate personnel to assume the responsibilities and duties as defined herein for their respective roles

CONDENSATION OF WATER VAPOR IN A VERTICAL TUBE CONDENSER

Directory of Open Access Journals (Sweden)

Jan Havlík

2015-10-01

Full Text Available This paper presents an analysis of heat transfer in the process of condensation of water vapor in a vertical shell-and-tube condenser. We analyze the use of the Nusselt model for calculating the condensation heat transfer coefficient (HTC inside a vertical tube and the Kern, Bell-Delaware and Stream-flow analysis methods for calculating the shell-side HTC from tubes to cooling water. These methods are experimentally verified for a specific condenser of waste process vapor containing air. The operating conditions of the condenser may be different from the assumptions adopted in the basic Nusselt theory. Modifications to the Nusselt condensation model are theoretically analyzed.

Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

International Nuclear Information System (INIS)

Warner, C.L.

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

Energy Technology Data Exchange (ETDEWEB)

Warner, C.L. (comp.)

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

Perceptions of Organizational Functioning in Substance Abuse Treatment Facilities in South Africa

Science.gov (United States)

Bowles, Steven; Louw, Johann; Myers, Bronwyn

2011-01-01

Directors' and treatment staff's perceptions of organizational functioning within substance abuse treatment facilities in four provinces in South Africa were examined via the Texas Christian University's Organizational Readiness for Change instrument. Forty-four treatment facilities (out of 89) participated in the study. Results indicated that…

Evaluation of Advanced Models for PAFS Condensation Heat Transfer in SPACE Code

Energy Technology Data Exchange (ETDEWEB)

Bae, Byoung-Uhn; Kim, Seok; Park, Yu-Sun; Kang, Kyung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ahn, Tae-Hwan; Yun, Byong-Jo [Pusan National University, Busan (Korea, Republic of)

2015-10-15

The PAFS (Passive Auxiliary Feedwater System) is operated by the natural circulation to remove the core decay heat through the PCHX (Passive Condensation Heat Exchanger) which is composed of the nearly horizontal tubes. For validation of the cooling and operational performance of the PAFS, PASCAL (PAFS Condensing Heat Removal Assessment Loop) facility was constructed and the condensation heat transfer and natural convection phenomena in the PAFS was experimentally investigated at KAERI (Korea Atomic Energy Research Institute). From the PASCAL experimental result, it was found that conventional system analysis code underestimated the condensation heat transfer. In this study, advanced condensation heat transfer models which can treat the heat transfer mechanisms with the different flow regimes in the nearly horizontal heat exchanger tube were analyzed. The models were implemented in a thermal hydraulic safety analysis code, SPACE (Safety and Performance Analysis Code for Nuclear Power Plant), and it was evaluated with the PASCAL experimental data. With an aim of enhancing the prediction capability for the condensation phenomenon inside the PCHX tube of the PAFS, advanced models for the condensation heat transfer were implemented into the wall condensation model of the SPACE code, so that the PASCAL experimental result was utilized to validate the condensation models. Calculation results showed that the improved model for the condensation heat transfer coefficient enhanced the prediction capability of the SPACE code. This result confirms that the mechanistic modeling for the film condensation in the steam phase and the convection in the condensate liquid contributed to enhance the prediction capability of the wall condensation model of the SPACE code and reduce conservatism in prediction of condensation heat transfer.

3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

None

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

Condensation of the steam in the horizontal steam line during cold water flooding

International Nuclear Information System (INIS)

Strubelj, L.; Tiselj, I.

2006-01-01

Direct contact condensation and condensation induced water-hammer in a horizontal pipe was experimentally investigated at PMK-2 test facility of the Hungarian Atomic Energy Research Institute KFKI. The experiment is preformed in the horizontal section of the steam line of the PMK-2 integral test facility. As liquid water floods the horizontal part of the pipeline, the counter current horizontally stratified flow is being observed. During the flooding of the steam line, the vapour-liquid interface area increases and therefore the vapour condensation rate and the vapour velocity also increase. Similar phenomena can occur in the cold/hot leg of the primary loop of PWR nuclear power plant during loss of coolant accident, when emergency core cooling system is activated. Water level at one cross-section and four local void fraction and temperature at the top of steam line was measured and compared with simulation. Condensed steam increases the water temperature that is why the local temperature measurements are the most important information, from which condensation rate can be estimated, since mass of condensed steam was not measured. Free surface simulation of the experiment with thermal phase change model is presented. Surface renewal concept with small eddies is used for calculation of heat transfer coefficient. With surface renewal theory we did not get results similar to experiment, that is why heat transfer coefficient was increased by factor 20. In simulation with heat transfer coefficient calculated with surface renewal concept bubble entrapment is due to reflection of the wave from the end of the pipe. When heat transfer coefficient is increased, condensation rate and steam velocity are also increased, bubble entrapment is due to Kelvin-Helmholtz instability of the free surface, and the results become similar to the measurements. (author)

Steam condenser

International Nuclear Information System (INIS)

Masuda, Fujio

1980-01-01

Purpose: To enable safe steam condensation by providing steam condensation blades at the end of a pipe. Constitution: When high temperature high pressure steam flows into a vent pipe having an opening under water in a pool or an exhaust pipe or the like for a main steam eacape safety valve, non-condensable gas filled beforehand in the steam exhaust pipe is compressed, and discharged into the water in the pool. The non-condensable gas thus discharged from the steam exhaust pipe is introduced into the interior of the hollow steam condensing blades, is then suitably expanded, and thereafter exhausted from a number of exhaust holes into the water in the pool. In this manner, the non-condensable gas thus discharged is not directly introduced into the water in the pool, but is suitable expanded in the space of the steam condensing blades to suppress extreme over-compression and over-expansion of the gas so as to prevent unstable pressure vibration. (Yoshihara, H.)

The Integral Test Facility Karlstein

Directory of Open Access Journals (Sweden)

Stephan Leyer

2012-01-01

Full Text Available The Integral Test Facility Karlstein (INKA test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein—a vessel with a design pressure of 11 MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event—for example pipe rupture.

Mixed and Low-Level Waste Treatment Facility Project

International Nuclear Information System (INIS)

1992-04-01

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies

Numerical simulation of the direct contact condensation phenomena for PTS-related in single and combined-effect thermal hydraulic test facilities using TransAT CMFD code

Energy Technology Data Exchange (ETDEWEB)

Kadi, Rabah, E-mail: kadi.rkhaled@hotmail.com [Laboratory for Thermal-Hydraulics, Nuclear Research Center of Birine (Algeria); Aissani, Slimane [Hydrocarbons and Chemistry Faculty, University of Boumerdes (Algeria); Bouam, Abdellah [Laboratory for Thermal-Hydraulics, Nuclear Research Center of Birine (Algeria)

2015-11-15

Highlights: • TransAT CMFD code application to DCC phenomenon. • LEIS methodology to predict the condensing steam flow rate. • Validation of interfacial phase-change heat transfer and turbulence models. • Correction of damping function at the free surface region. • Numerical validation of previous models using LIM and KAERI & KAIST test facilities. - Abstract: The use of CFD for the industrial studies related to PTS, including DCC is already possible; improvements of the two-phase modeling capabilities have to be undertaken to qualify the codes for the simulation of such flows. The DCC in horizontally stratified flow regime constitutes very considerable challenge exercises for a computational fluid dynamics (CFD) simulation of the thermal hydraulics PTS phenomenon because the interplay between turbulence and interfacial heat and mass transfer problem. The main purpose of our study is to investigate numerically the DCC in horizontally stratified steam water flow in a 2D and 3D channel using TransAT CMFD code. The new methodology known as Large-Eddy & Interface (LEIS) have been implemented for treatment of turbulence combined with interface tracking ITM (level set approach). Among of the so-called ‘coarse-grained’ ITM's models, the modified original surface divergence has been chosen as well as the treatment of the turbulence by URANS and VLES. This contribution addressed on the validation of interfacial phase-change heat transfer and turbulence models with special correction of the damping function at the free surface for single and combined-effect thermal hydraulic studies for LIM and KAERI & KAIST test facilities. The LIES methodology was found to apply successfully to predict the condensing steam flow rate in the all cases of the LIM test case involving a Smooth to Wavy turbulent, concurrent stratified steam-water flow in a 2D channel. The CMFD TransAT code predicting capability is analyzed, comparing the liquid temperature and to much the

Preventing freezing of condensate inside tubes of air cooled condenser

International Nuclear Information System (INIS)

Joo, Jeong A; Hwang, In Hwan; Lee, Dong Hwan; Cho, Young Il

2012-01-01

An air cooled condenser is a device that is used for converting steam into condensate by using ambient air. The air cooled condenser is prone to suffer from a serious explosion when the condensate inside the tubes of a heat exchanger is frozen; in particular, tubes can break during winter. This is primarily due to the structural problem of the tube outlet of an existing conventional air cooled condenser system, which causes the backflow of residual steam and noncondensable gases. To solve the backflow problem in such condensers, such a system was simulated and a new system was designed and evaluated in this study. The experimental results using the simulated condenser showed the occurrence of freezing because of the backflow inside the tube. On the other hand, no backflow and freezing occurred in the advanced new condenser, and efficient heat exchange occurred

Condensate subcooling near tube exit during horizontal in-tube condensation

International Nuclear Information System (INIS)

Hashizume, K.; Abe, N.; Ozeki, T.

1992-01-01

In-tube condensation is encountered in various applications for heat exchangers, such as domestic air-conditioning equipment, industrial air-cooled condensers, and moisture separator reheaters (MSRs) for nuclear power pants. Numerous research work has been conducted to predict the condensation heat transfer coefficient, and we have now enough information for thermal design of heat exchangers with horizontal in-tube condensation. Most of the research is analytical and/or experimental work in the annular or stratified flow regime, or experimental work on bulk condensation, i.e., from saturated vapor to complete condensation. On the other hand, there exist few data about the heat transfer phenomena in the very lower-quality region near the tube exit. The purpose of this paper is to clarify the condensation heat transfer phenomena near the tube exit experimentally and analytically, and to predict the degree of condensate subcooling

Mixed convection heat transfer between a steam / non-condensable gas mixture and an inclined finned tube bundle

Energy Technology Data Exchange (ETDEWEB)

Cachard, F. de; Lomperski, S.; Monauni, G.R. [Paul Scherrer Inst. (PSI), Villigen (Switzerland). Lab. for Thermal-Hydraulics

1999-07-01

An experimental and analytical program was performed at PSI to study the performance of a finned-tube condenser in the presence of non-condensable gases at low gas mass fluxes. The model developed for this application includes mixed convection heat transfer between the vapour/non-condensable mixture and the finned-tubes, heat conduction through the fins and tubes, and evaporative heat transfer inside the tubes. The finned-tubes condenser model has been assessed against data obtained at the PSI LINX facility with two test condensers. For the 62 LINX experiments performed, the model predictions are very good, i.e., less than 10 % standard deviation between experimental and predicted results. (authors)

Dual approaches for defects condensation

Energy Technology Data Exchange (ETDEWEB)

Rougemont, Romulo; Grigorio, Leonardo de Souza; Wotzasek, Clovis [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil); Guimaraes, Marcelo Santos [Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil)

2009-07-01

Full text. Due to the fact that the QCD running coupling constant becomes larger as we go into the low energy (or large distance) limit of the theory, a perturbative treatment of its infrared (IR) region is impossible. In particular, a formal mathematical demonstration of color confinement and a complete physical understanding of the exact mechanism that confines quarks and gluons are two missing points in our current knowledge of the IR-QCD. It was known that due to the Meissner effect of expulsion of magnetic fields in a electric condensate that usual superconductors should confine magnetic monopoles. That point led to the conjecture that the QCD vacuum could be a condensate of chromomagnetic monopoles, a dual superconductor (DSC). Such a chromomagnetic condensate should be responsible for the dual Meissner effect which is expected to lead to the confinement of color charges immersed in this medium. In dual superconductor models of color confinement, magnetic monopoles appear as topological defects in points of the space where the abelian projection becomes singular. Also, condensation of other kinds of defects such as vortices in superfluids and line-like defects in solids are responsible for a great variety of phase transitions, which once more proves the relevance of the subject. In the present work we review two methods that allow us to approach the condensation of defects: the Kleinert Mechanism (KM) and the Julia-Toulouse Mechanism (JTM). We show that in the limit where the vortex gauge field goes to zero, which we identify as the signature of the condensation of defects in the dual picture, these are two equivalent dual prescriptions for obtaining an effective theory for a phase where defects are condensed, starting from the fundamental theory defined in the normal phase where defects are diluted. (author)

Nuclear reactor containing facility

International Nuclear Information System (INIS)

Hidaka, Masataka; Murase, Michio.

1994-01-01

In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

A macrothermodynamic approach to the limit of reversible capillary condensation.

Science.gov (United States)

Trens, Philippe; Tanchoux, Nathalie; Galarneau, Anne; Brunel, Daniel; Fubini, Bice; Garrone, Edoardo; Fajula, François; Di Renzo, Francesco

2005-08-30

The threshold of reversible capillary condensation is a well-defined thermodynamic property, as evidenced by corresponding states treatment of literature and experimental data on the lowest closure point of the hysteresis loop in capillary condensation-evaporation cycles for several adsorbates. The nonhysteretical filling of small mesopores presents the properties of a first-order phase transition, confirming that the limit of condensation reversibility does not coincide with the pore critical point. The enthalpy of reversible capillary condensation can be calculated by a Clausius-Clapeyron approach and is consistently larger than the condensation heat in unconfined conditions. Calorimetric data on the capillary condensation of tert-butyl alcohol in MCM-41 silica confirm a 20% increase of condensation heat in small mesopores. This enthalpic advantage makes easier the overcoming of the adhesion forces by the capillary forces and justifies the disappearing of the hysteresis loop.

Waste analysis plan for the 200 area effluent treatment facility and liquid effluent retention facility

International Nuclear Information System (INIS)

Ballantyne, N.A.

1995-01-01

This waste analysis plan (WAP) has been prepared for startup of the 200 Area Effluent Treatment Facility (ETF) and operation of the Liquid Effluent Retention Facility (LERF), which are located on the Hanford Facility, Richland, Washington. This WAP documents the methods used to obtain and analyze representative samples of dangerous waste managed in these units, and of the nondangerous treated effluent that is discharged to the State-Approved Land Disposal System (SALDS). Groundwater Monitoring at the SALDS will be addressed in a separate plan

Operation technology of air treatment system in nuclear facilities

CERN Document Server

Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

2001-01-01

Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

Technical study of a thermally dense long term interim storage facility

International Nuclear Information System (INIS)

Le Duigou, A.; Badie, M.; Duret, B.; Bricard, A.

2001-01-01

The COFRE concept is aimed at the surface and thermal densification of the interim storage facility for irradiated fuels. The facility provides the biological shielding. A conditioning cell is used to load and retrieve the fuel assemblies. The facility container is the second containment barrier. The high power levels are managed by an auxiliary cooling system whose original feature is the passive use of a water evaporation-condensation cycle in a sealed circuit. The removable evaporator abuts the container. The air cooled condenser is placed outside the facility. Contact resistance and heat pipe mode were successfully modelled and are undergoing experimental validation on the THERESE and REBECA loops. (author)

EPA Facility Registry Service (FRS): Wastewater Treatment Plants

Data.gov (United States)

U.S. Environmental Protection Agency — This GIS dataset contains data on wastewater treatment plants, based on EPA's Facility Registry Service (FRS), EPA's Integrated Compliance Information System (ICIS)...

Conceptual design study advanced concepts test (ACT) facility

Energy Technology Data Exchange (ETDEWEB)

Zaloudek, F.R.

1978-09-01

The Advanced Concepts Test (ACT) Project is part of program for developing improved power plant dry cooling systems in which ammonia is used as a heat transfer fluid between the power plant and the heat rejection tower. The test facility will be designed to condense 60,000 lb/hr of exhaust steam from the No. 1 turbine in the Kern Power Plant at Bakersfield, CA, transport the heat of condensation from the condenser to the cooling tower by an ammonia phase-change heat transport system, and dissipate this heat to the environs by a dry/wet deluge tower. The design and construction of the test facility will be the responsibility of the Electric Power Research Institute. The DOE, UCC/Linde, and the Pacific Northwest Laboratories will be involved in other phases of the project. The planned test facilities, its structures, mechanical and electrical equipment, control systems, codes and standards, decommissioning requirements, safety and environmental aspects, and energy impact are described. Six appendices of related information are included. (LCL)

Improvement of direct contact condensation model of relap5/mod3.1 for passive high-pressure injection system

International Nuclear Information System (INIS)

Sang, Il Lee; Hee, Cheon No

1998-01-01

A simple set of the transition criterion of the condensation regimes and the heat transfer coefficients on the direct contact condensation in the core makeup tank was developed, and implemented in RELAP5/MOD3.1. The condensation regimes were divided into two ones: supply limit and condensation limit. In modeling the transition criterion between two regimes, a large-eddy model developed by Theofanous was used. The modified code better predicted the experiments on the core makeup tank using small scale test facility than the original code did

Disposal of aqueous condensate from high efficiency gas boilers

Energy Technology Data Exchange (ETDEWEB)

Hardwick, G J; Pattison, J R

1984-01-01

If highly efficient gas-fired condensing heating appliances are installed in Britain, the aqueous condensate produced can be conveniently run into existing sewage drains. The part of the drainage system that is most vulnerable to corrosion from the mildly acid condensate is that portion adjacent to the domestic premises. The tests described indicate that this is not at risk and the only precaution that might be considered necessary is to avoid running the condensate over galvanized drain covers in order to prevent unsightly staining. Water authorities in Britain and detailed studies in the US and Holland confirm that the condensate - after dilution by domestic waste, sewage, and rainwater - would be harmless to municipal sewage systems and would not, either in volume or chemical composition, affect the working of existing sewage treatment plants.

Ventilation and air conditioning system in waste treatment and storage facilities

International Nuclear Information System (INIS)

Kinoshita, Hirotsugu; Sugawara, Kazushige.

1987-01-01

So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

Emergency reactor core cooling facility

International Nuclear Information System (INIS)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka.

1996-01-01

The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

Emergency reactor core cooling facility

Energy Technology Data Exchange (ETDEWEB)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka

1996-11-01

The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

Hydrogen behavior in ice condenser containments

Energy Technology Data Exchange (ETDEWEB)

Lundstroem, P.; Hongisto, O. [Power Plant Lab., Helsinki (Finland); Theofanous, T.G. [Univ. of California, Santa Barbara, CA (United States)] [and others

1995-09-01

A new hydrogen management strategy is being developed for the Loviisa ice condenser containment. The strategy relies on containment-wide natural circulations that develop, once the ice condenser doors are forced open, to effectively produce a well-mixed behavior, and a correspondingly slow rise in hydrogen concentration. Levels can then be kept low by a distributed catalytic recombiner system, and (perhaps) an igniter system as a backup, while the associated energy releases can be effectively dissipated in the ice bed. Verification and fine-tuning of the approach is carried out experimentally in the VICTORIA facility and by associated scaling/modelling studies. VICTORIA represents an 1/15th scale model of the Loviisa containment, hydrogen is simulated by helium, and local concentration measurements are obtained by a newly developed instrument specifically for this purpose, called SPARTA. This paper is focused on experimental results from several key experiments that provide a first delineation of key behaviors.

Startup of the remote laboratory-scale waste-treatment facility

International Nuclear Information System (INIS)

Knox, C.A.; Siemens, D.H.; Berger, D.N.

1981-01-01

The Remote Laboratory-Scale Waste-Treatment Facility was designed as a system to solidify small volumes of radioactive liquid wastes. The objectives in operating this facility are to evaluate solidification processes, determine the effluents generated, test methods for decontaminating the effluents, and provide radioactive solidified waste products for evaluation. The facility consists of a feed-preparation module, a waste-solidification module and an effluent-treatment module. The system was designed for remote installation and operation. Several special features for remotely handling radioactive materials were incorporated into the design. The equipment was initially assembled outside of a radiochemical cell to size and fabricate the connecting jumpers between the modules and to complete some preliminary design-verification tests. The equipment was then disassembled and installed in the radiochemical cell. When installation was completed the entire system was checked out with water and then with a nonradioactive simulated waste solution. The purpose of these operations was to start up the facility, find and solve operational problems, verify operating procedures and train personnel. The major problems experienced during these nonradioactive runs were plugging of the spray calciner nozzle and feed tank pumping failures. When these problems were solved, radioactive operations were started. This report describes the installation of this facility, its special remote design feature and the startup operations

Treatment of DOE mixed wastes using commercial facilities

International Nuclear Information System (INIS)

Kramer, J.F.; Ross, M.A.; Dilday, D.R.

1992-02-01

In a demonstration program, Department of Energy (DOE) solid mixed wastes generated during uranium processing operations are characterized to define the unit operations required for treatment. The objectives included the implementation of these treatment operations utilizing a commercial Treatment, Storage and Disposal Facility (TSDF). In contracting for commercial hazardous and mixed waste treatment, it is important to characterize the waste beyond the identification of toxicity characteristic (TC) and radiological content. Performing treatability studies and verification of all the unit operations required for treatment is critical. The stream selected for this program was TC hazardous for barium (D005) and contaminated with both depleted and low enriched uranium. The program resulted in the generation of characterization data and treatment strategies. The characterization and treatability studies indicated that although a common unit operation was required to remove the toxic characteristic, multiple pretreatment operations were needed. Many of these operations do not exist at available TSDF's, rendering some portions of the stream untreatable using existing commercial TSDF's. For this project the need for pretreatment operations resulted in only a portion of the waste originally targeted for treatment being accepted for treatment at a commercial TSDF. The majority of the targeted stream could not be successfully treated due to lack of an off-site commercial treatment facility having the available equipment and capacity or with the correct combination of RCRA permits and radioactive material handling licenses. This paper presents a case study documenting the results of the project

Importance of water Influx and waterflooding in Gas condensate reservoir

OpenAIRE

Ali, Faizan

2014-01-01

The possibility of losing valuable liquid and lower gas well deliverability have made gas condensate reservoirs very important and extra emphasizes are made to optimize hydrocarbon recovery from a gas condensate reservoir. Methods like methanol treatments, wettability alteration and hydraulic fracturing are done to restore the well deliverability by removing or by passing the condensate blockage region. The above mentioned methods are applied in the near wellbore region and only improve the w...

Conceptual design of tritium treatment facility

International Nuclear Information System (INIS)

Tachikawa, Katsuhiro

1982-01-01

In connection with the development of fusion reactors, the development of techniques concerning tritium fuel cycle, such as the refining and circulation of fuel, the recovery of tritium from blanket, waste treatment and safe handling, is necessary. In Japan Atomic Energy Research Institute, the design of the tritium process research laboratory has been performed since fiscal 1977, in which the following research is carried out: 1) development of hydrogen isotope separation techniques by deep cooling distillation method and thermal diffusion method, 2) development of the refining, collection and storage techniques for tritium using metallic getters and palladium-silver alloy films, and 3) development of the safe handling techniques for tritium. The design features of this facility are explained, and the design standard for radiation protection is shown. At present, in the detailed design stage, the containment of tritium and safety analysis are studied. The building is of reinforced concrete, and the size is 48 m x 26 m. Glove boxes and various tritium-removing facilities are installed in two operation rooms. Multiple wall containment system and tritium-removing facilities are explained. (Kako, I.)

Water Condensation

DEFF Research Database (Denmark)

Jensen, Kasper Risgaard; Fojan, Peter; Jensen, Rasmus Lund

2014-01-01

The condensation of water is a phenomenon occurring in multiple situations in everyday life, e.g., when fog is formed or when dew forms on the grass or on windows. This means that this phenomenon plays an important role within the different fields of science including meteorology, building physics......, and chemistry. In this review we address condensation models and simulations with the main focus on heterogeneous condensation of water. The condensation process is, at first, described from a thermodynamic viewpoint where the nucleation step is described by the classical nucleation theory. Further, we address...

Treatability studies of alternative wastewaters for Metal Finishing Effluent Treatment Facility

International Nuclear Information System (INIS)

Wittry, D.M.; Martin, H.L.

1994-01-01

The 300-M Area Liquid Effluent Treatment Facility (LETF) of the Savannah River Site (SRS) is an end-of-pipe industrial wastewater treatment facility that uses precipitation and filtration, which is the EPA Best Available Technology economically achievable for a Metal Finishing and Aluminum Form Industries. Upon the completion of stored waste treatment, the LETF will be shut down, because production of nuclear materials for reactors stopped at the end of the Cold War. The economic use of the LETF for the treatment of alternative wastewater streams is being evaluated through laboratory bench-scale treatability studies

The PANDA facility and first test results

International Nuclear Information System (INIS)

Dreier, J.; Huggenberger, M.; Aubert, C.; Bandurski, T.; Fischer, O.; Healzer, J.; Lomperski, S.; Strassberger, H.J.; Varadi, G.; Yadigaroglu, G.

1996-01-01

The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and non-condensable gases in the system. The facility is in 1:1 vertical scale and 1:25 scale for volume, power etc. Extensive facility characterization tests and steady-state passive containment condenser performance tests are presented. The results of the base case test of a series of transient system behaviour tests are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the Simplified Boiling Water Reactor's containment is likely to be favorably responsive and highly robust to changes in the thermal transport patterns. (orig.) [de

40 CFR 403.19 - Provisions of specific applicability to the Owatonna Waste Water Treatment Facility.

Science.gov (United States)

2010-07-01

... the Owatonna Waste Water Treatment Facility. 403.19 Section 403.19 Protection of Environment... Owatonna Waste Water Treatment Facility. (a) For the purposes of this section, the term “Participating... Industrial User discharging to the Owatonna Waste Water Treatment Facility in Owatonna, Minnesota, when a...

Computational fluid dynamics validation study of steam condensation on the containment walls

International Nuclear Information System (INIS)

Gera, B.; Sharma, P.K.; Singh, R.K.; Vaze, K.K.

2012-01-01

In water cooled power reactors, significant quantities of hydrogen could be produced following a severe accident (loss-of-coolant-accident along with non availability of emergency core cooling system). A sound understanding of dispersion, stratification and diffusion of released hydrogen during severe accidents is, therefore, of practical importance and use to better understand the possibility of ignition, combustion and explosion of such releases within the context of containment safety. The presence of air and steam in the containment atmosphere also affects the hydrogen distribution as steam condensation takes place at containment walls in presence of non condensable and bulk of the mixture diffuses towards wall. The application of general purpose CFD codes for the analysis of the hydrogen behaviour within NPP containments during severe accidents has been increasing over past few years. The commercial CFD codes generally do not have built-in steam condensations models. In the present work, the adaptation of a commercial multipurpose code to this kind of problem is explained, i.e. by the implementation of models for steam condensation onto walls in presence of non-condensable gases. Steam condensation was modeled using the Uchida correlation, which was originally developed to be used for 'lumped' (volume-averaged) modeling of steam condensation in the presence of non-condensable gases. The Uchida correlation is based on experiments on natural convection from relatively small vertical plates. The present methodology has been validated against experimental data from the TOSQAN and COPAIN experimental facilities. (orig.)

Construction of the two-phase critical flow test facility

International Nuclear Information System (INIS)

Chung, C. H.; Chang, S. K.; Park, H. S.; Min, K. H.; Choi, N. H.; Kim, C. H.; Lee, S. H.; Kim, H. C.; Chang, M. H.

2002-03-01

The two-phase critical test loop facility has been constructed in the KAERI engineering laboratory for the simulation of small break loss of coolant accident entrained with non-condensible gas of SMART. The test facility can operate at 12 MPa of pressure and 0 to 60 C of sub-cooling with 0.5 kg/s of non- condensible gas injection into break flow, and simulate up to 20 mm of pipe break. Main components of the test facility were arranged such that the pressure vessel containing coolant, a test section simulating break and a suppression tank inter-connected with pipings were installed vertically. As quick opening valve opens, high pressure/temperature coolant flows through the test section forming critical two-phase flow into the suppression tank. The pressure vessel was connected to two high pressure N2 gas tanks through a control valve to control pressure in the pressure vessel. Another N2 gas tank was also connected to the test section for the non-condensible gas injection. The test facility operation was performed on computers supported with PLC systems installed in the control room, and test data such as temperature, break flow rate, pressure drop across test section, gas injection flow rate were all together gathered in the data acquisition system for further data analysis. This test facility was classified as a safety related high pressure gas facility in law. Thus the loop design documentation was reviewed, and inspected during construction of the test loop by the regulatory body. And the regulatory body issued permission for the operation of the test facility

Assessment of the proposed decontamination and waste treatment facility at LLNL

International Nuclear Information System (INIS)

Cohen, J.J.

1987-01-01

To provide a centralized decontamination and waste treatment facility (DWTF) at LLNL, the construction of a new installation has been planned. Objectives for this new facility were to replace obsolete, structurally and environmentally sub-marginal liquid and solid waste process facilities and decontamination facility and to bring these facilities into compliance with existing federal, state and local regulations as well as DOE orders. In a previous study, SAIC conducted a preliminary review and evaluation of existing facilities at LLNL and cost effectiveness of the proposed DWTF. This document reports on a detailed review of specific aspects of the proposed DWTF

9 CFR 3.126 - Facilities, indoor.

Science.gov (United States)

2010-01-01

..., vents, fans, or air-conditioning and shall be ventilated so as to minimize drafts, odors, and moisture condensation. (c) Lighting. Indoor housing facilities shall have ample lighting, by natural or artificial means...

Measurement of Total Condensation on a Shrouded Cryogenic Surface using a Single Quart Crystal Microbalance

International Nuclear Information System (INIS)

Haid, B.J.; Malsbury, T.N.; Gibson, C.R.; Warren, C.T.

2008-01-01

A single quartz crystal microbalance (QCM) is cooled to 18 K to measure condensation rates inside of a retractable ''shroud'' enclosure. The shroud is of a design intended to minimize condensate on fusion targets to be fielded at the National Ignition Facility (NIF). The shroud has a double-wall construction with an inner wall that may be cooled to 75-100 K. The QCM and the shroud system were mounted in a vacuum chamber and cooled using a cryocooler. Condensation rates were measured at various vacuum levels and compositions, and with the shroud open or closed. A technique for measuring total condensate during the cooldown of the system with an accuracy of better than 1.0 x 10 -6 g/cm 2 was also demonstrated. The technique involved a separate measurement of the condensate-free crystal frequency as a function of temperature that was later applied to the measurement of interest

Experimental Investigation of Operation of VVER Steam Generator in Condensation Mode in the Event of the Severe Accident

Energy Technology Data Exchange (ETDEWEB)

Morozov, Andrey [Institute for Physics and Power Engineering by A.I. Leypunsky, 1 Bondarenko sq. Obninsk, 249033 (Russian Federation)

2008-07-01

For new Russian nuclear power plants with VVER-1200 reactor in the event of a beyond design basis accident, provision is made for the use of passive safety systems for necessary core cooling. These safety systems include the passive heat removal system (PHRS). In the case of leakage in the primary circuit this system assures the transition of steam generators (SG) to operation in the mode of condensation of the primary circuit steam. As a result, the condensate from SG arrives at the core providing its additional cooling. To investigate the condensation mode of VVER SG operation, a large scale HA2M-SG test facility was constructed. The rig incorporates: buffer tank, SG model with scale is 1:46, PHRS heat exchanger. Experiments at the test facility have been performed to investigate condensation mode of operation of SG model at the pressure 0.4 MPa, correspond to VVER reactor pressure at the last stage of the beyond design basis accident. The report presents the test procedure and the basic obtained test results. (authors)

Performance of evaporative condensers

Energy Technology Data Exchange (ETDEWEB)

Ettouney, Hisham M.; El-Dessouky, Hisham T.; Bouhamra, Walid; Al-Azmi, Bader

2001-07-01

Experimental investigation is conducted to study the performance of evaporative condensers/coolers. The analysis includes development of correlations for the external heat transfer coefficient and the system efficiency. The evaporative condenser includes two finned-tube heat exchangers. The system is designed to allow for operation of a single condenser, two condensers in parallel, and two condensers in series. The analysis is performed as a function of the water-to-air mass flow rate ratio (L/G) and the steam temperature. Also, comparison is made between the performance of the evaporative condenser and same device as an air-cooled condenser. Analysis of the collected data shows that the system efficiency increases at lower L/G ratios and higher steam temperatures. The system efficiency for various configurations for the evaporative condenser varies between 97% and 99%. Lower efficiencies are obtained for the air-cooled condenser, with values between 88% and 92%. The highest efficiency is found for the two condensers in series, followed by two condensers in parallel and then the single condenser. The parallel condenser configuration can handle a larger amount of inlet steam and can provide the required system efficiency and degree of subcooling. The correlation for the system efficiency gives a simple tool for preliminary system design. The correlation developed for the external heat transfer coefficient is found to be consistent with the available literature data. (Author)

Condensation of steam

International Nuclear Information System (INIS)

Prisyazhniuk, V.A.

2002-01-01

An equation for nucleation kinetics in steam condensation has been derived, the equation taking into account the concurrent and independent functioning of two nucleation mechanisms: the homogeneous one and the heterogeneous one. The equation is a most general-purpose one and includes all the previously known condensation models as special cases. It is shown how the equation can be used in analyzing the process of steam condensation in the condenser of an industrial steam-turbine plant, and in working out new ways of raising the efficiency of the condenser, as well as of the steam-turbine plant as a whole. (orig.)

Condensation During Nuclear Reactor Loca

International Nuclear Information System (INIS)

Rihan, Y.; Teamah, M.; Sorour, M.; Soliman, S.

2008-01-01

Two-phase channel flow with condensation is a common phenomenon occurs in a number of nuclear reactor accident scenarios. It also plays an important role during the operation of the safety coolant injection systems in advanced nuclear reactors. Semiempirical correlations and simple models based on the analogy between heat and mass transfer processes have been previously applied. Rigorous models, compatible with the state-of-the-art numerical algorithms used in thermal-hydraulic computer codes, are scare, and are of great interest. The objective of this research is to develop a method for modeling condensation, with noncondensable gases, compatible with the state-of-the-art numerical methods for the solution of multi-phase field equations. A methodology for modeling condensation, based on the stagnant film theory, and compatible with the reviewed numerical algorithms, is developed. The model treats the coupling between the heat and mass transfer processes, and allows for an implicit treatment of the mass and momentum exchange terms as the gas-liquid interphase, without iterations. The developed model was used in the application of loss of coolant in pressurized water reactor accidents

Modelling of condensation phenomena

International Nuclear Information System (INIS)

Jeong, Jae Jun; Chang, Won Pyo

1996-07-01

Condensation occurs when vapor is cooled sufficiently below the saturation temperature to induce the nucleation of droplets. Such nucleation may occur homogeneously within the vapor or heterogeneously on entrained particular matter. Heterogeneous nucleation may occur on the walls of the system, where the temperature is below the saturation temperature. There are two forms of heterogeneous condensation, drop-wise and film-wise. Another form of condensation occurs when vapor directly contacts to subcooled liquid. In nuclear power plant systems, all forms of condensation may occur during normal operation or accident conditions. In this work the modelling of condensation is surveyed, including the Nusselts' laminar film condensation theory in 1916, Rohsenow's turbulent film condensation model in 1950s, and Chen's models in 1987. Major attention is paid on the film condensation models among various research results because of its importance in engineering applications. It is found that theory, experiment, and empirical correlations for film condensation are well established, but research for drop-wise and direct-contact condensation are not sufficient yet. Condensation models in the best-estimate system codes such as RELAP5/MOD3 and CATHARE2 are also investigated. 3 tabs., 11 figs., 36 refs. (Author)

Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary

International Nuclear Information System (INIS)

1995-01-01

This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals

Improved condenser design and condenser-fan operation for air-cooled chillers

International Nuclear Information System (INIS)

Yu, F.W.; Chan, K.T.

2006-01-01

Air-cooled chillers traditionally operate under head pressure control via staging constant-speed condenser fans. This causes a significant drop in their coefficient of performance (COP) at part load or low outdoor temperatures. This paper describes how the COP of these chillers can be improved by a new condenser design, using evaporative pre-coolers and variable-speed fans. A thermodynamic model for an air-cooled screw-chiller was developed, within which the condenser component considers empirical equations showing the effectiveness of an evaporative pre-cooler in lowering the outdoor temperature in the heat-rejection process. The condenser component also contains an algorithm to determine the number and speed of the condenser fans staged at any given set point of condensing temperature. It is found that the chiller's COP can be maximized by adjusting the set point based on any given chiller load and wet-bulb temperature of the outdoor air. A 5.6-113.4% increase in chiller COP can be achieved from the new condenser design and condenser fan operation. This provides important insights into how to develop more energy-efficient air-cooled chillers

Proceedings: Condenser technology conference

International Nuclear Information System (INIS)

Tsou, J.L.; Mussalli, Y.G.

1991-08-01

Seam surface condenser and associated systems performance strongly affects availability and heat rate in nuclear and fossil power plants. Thirty-six papers presented at a 1990 conference discuss research results, industry experience, and case histories of condenser problems and solutions. This report contains papers on life extension, performance improvement, corrosion and failure analysis, fouling prevention, and recommendation for future R ampersand D. The information represents recent work on condenser problems and solutions to improve the procurement, operation, and maintenance functions of power plant personnel. Several key points follow: A nuclear and a fossil power plant report show that replacing titanium tube bundles improves condenser availability and performance. One paper reports 10 years of experience with enhanced heat transfer tubes in utility condensers. The newly developed enhanced condenser tubes could further improve condensing heat transfer. A new resistance summation method improves the accuracy of condenser performance prediction, especially for stainless steel and titanium tubed condensers. Several papers describe improved condenser fouling monitoring techniques, including a review of zebra mussel issues

Organic constituents in sour condensates from shale-oil and petroleum-crude runs at Sohio's Toledo refinery: identification and wastewater-control-technology considerations

Energy Technology Data Exchange (ETDEWEB)

Wingender, R J; Harrison, W; Raphaelian, L A

1981-02-01

Samples of sour condensate generated from the continuous processing of both crude shale oil and petroleum crude were collected and extracted with methylene chloride. The extracts were analyzed using capillary-column gas chromatography/mass spectrometry at Argonne National Laboratory and Radian Corporation. Qualitatively, the predominant types of organic compounds present in the shale-oil sour condensate were pyridines and anilines; semiquantitatively, these compounds were present at a concentration of 5.7 ppM, or about 78% of the total concentration of components detected. In contrast, straight-chain alkanes were the predominant types of compounds found in the sour condensate produced during isocracking of conventional crude oil. The approximate concentration of straight-chain alkanes, 8.3 ppM, and of other branched and/or unsaturated hydrocarbons, 6.8 ppM, amounted to 88% of the total concentration of components detected in the sour condensate from the petroleum-crude run. Nitrogen compounds in the shale-oil sour condensate may necessitate alterations of the sour water and refinery wastewater-treatment facilities to provide for organics degradation and to accommodate the potentially greater ammonia loadings. This would include use of larger amounts of caustic to enhance ammonia removal by steam stripping. Possible problems associated with biological removal of organic-nitrogen compounds should be investigated in future experimental shale-oil refining runs.

On the Bose-Einstein condensation of an ideal gas

International Nuclear Information System (INIS)

Landau, L.J.; Wilde, I.F.

1979-01-01

A mathematically precise treatment is given of the well-known Bose-Einstein condensation of an ideal gas in the grand canonical ensemble at fixed density. The method works equally well for any of the standard boundary conditions and it is shown that the finite volume activity converges and that in three dimensions condensation occurs for Dirichlet, Neumann, periodic, and repulsive walls. (orig.) 891 HJ/orig. 892 CKA

Condensate cleaning systems

International Nuclear Information System (INIS)

Yamamoto, Michiyoshi; Oosumi, Katsumi; Takashima, Yoshie; Mitani, Shinji.

1982-01-01

Purpose: To decrease the frequency for the backwash and regeneration operations due to the increase in the differential pressure resulted from claddings captured in a mixed floor type desalter, and decrease the amount of radioactive liquid wastes of claddings from the condensate systems by removing claddings with electromagnetic filters. Constitution: In an existent plant, a valves is disposed between a condensate pump and a mixed floor type desalter. A pipeway is branched from a condensate pipe between the condensate pipe and the valve, through which condensates are transferred by a pump to an electromagnetic filter such as of a high gradient type electromagntic filter to remove claddings, then returned to a condensate pipe between the valve and the mixed floor type desalter and, thereafter, are removed with ionic components in the mixed floor type desalter and fed to the reactor. (Yoshino, Y.)

Phase 2 testing results of immobilization of WTP effluent management facility vaporator bottoms simulant

Energy Technology Data Exchange (ETDEWEB)

Reigel, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-09-08

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate) from the primary off-gas system. This work examined three waste form formulations based on previous testing with related simulants: 8 wt% ordinary portland cement (OPC), 47 wt% blast furnace slag (BFS), 45 wt% fly ash (FA) known as Cast Stone formulation; 20 wt% Aquaset® II-GH and 80 wt% BFS; 20 wt% OPC and 80 wt% BFS. These tests successfully produced one waste form that set within five days (Cast Stone formulation); however the other two formulations, Aquaset® II-GH/BFS and OPC/BFS, took approximately eight and fourteen days to set, respectively.

DWTF [decontamination and waste treatment facilities] assessment

International Nuclear Information System (INIS)

Maimoni, A.

1986-01-01

The purpose of this study has been to evaluate the adequacy of present and proposed decontamination and waste treatment facilities (DWTF) at LLNL, to determine the cost effectiveness for proposed improvements, and possible alternatives for accomplishing these improvements. To the extent possible, we have also looked at some of the proposed environmental compliance and cleanup (ECC) projects

Condensation heat transfer with noncondensable gas for passive containment cooling of nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Leonardi, Tauna [Schlumberger, 14910 Airline Rd., Rosharon, TX 77583 (United States)]. E-mail: Tleonardi@slb.com; Ishii, Mamoru [School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States)]. E-mail: Ishii@ecn.purdue.edu

2006-09-15

Noncondensable gases that come from the containment and the interaction of cladding and steam during a severe accident deteriorate a passive containment cooling system's performance by degrading the heat transfer capabilities of the condensers in passive containment cooling systems. This work contributes to the area of modeling condensation heat transfer with noncondensable gases in integral facilities. Previously existing correlations and models are for the through-flow of the mixture of steam and the noncondensable gases and this may not be applicable to passive containment cooling systems where there is no clear passage for the steam to escape. This work presents a condensation heat transfer model for the downward cocurrent flow of a steam/air mixture through a condenser tube, taking into account the atypical characteristics of the passive containment cooling system. An empirical model is developed that depends on the inlet conditions, including the mixture Reynolds number and noncondensable gas concentration.

Overview of a conceptualized waste water treatment facility for the Consolidated Incinerator Facility

International Nuclear Information System (INIS)

McCabe, D.J.

1992-01-01

The offgas system in the Consolidated Incinerator Facility (CIF) will generate an aqueous waste stream which is expected to contain hazardous, nonhazardous, and radioactive components. The actual composition of this waste stream will not be identified until startup of the facility, and is expected to vary considerably. Wastewater treatment is being considered as a pretreatment to solidification in order to make a more stable final waste form and to reduce disposal costs. A potential treatment scenario has been defined which may allow disposition of this waste in compliance with all applicable regulations. The conceptualized wastewater treatment plant is based on literature evaluations for treating hazardous metals. Laboratory tests hwill be run to verify the design for its ability to remove the hazardous and radioactive components from this waste stream. The predominant mechanism employed for removal of the hazardous and radioactive metal ions is coprecipitation. The literature indicates that reasonably low quantities of hazardous metals can be achieved with this technique. The effect on the radioactive metal ions is not predictable and has not been tested. The quantity of radioactive metal ions predicted to be present in the waste is significantly less than the solubility limit of those ions, but is higher than the discharge guidelines established by DOE Order 5400.5

Condensation coefficient of water in a weak condensation state

International Nuclear Information System (INIS)

Kobayashi, Kazumichi; Watanabe, Shunsuke; Yamano, Daigo; Yano, Takeru; Fujikawa, Shigeo

2008-01-01

The condensation coefficient of water at a vapor-liquid interface is determined by combining shock tube experiments and numerical simulations of the Gaussian-BGK Boltzmann equation. The time evolution in thickness of a liquid film, which is formed on the shock tube endwall behind the shock wave reflected at the endwall, is measured with an optical interferometer consisting of the physical beam and the reference one. The reference beam is utilized to eliminate systematic noises from the physical beam. The growth rate of the film is evaluated from the measured time evolution and it is incorporated into the kinetic boundary condition for the Boltzmann equation. From a numerical simulation using the boundary condition, the condensation coefficient of water is uniquely deduced. The results show that, in a condition of weak condensation near a vapor-liquid equilibrium state, the condensation coefficient of water is almost equal to the evaporation coefficient estimated by molecular dynamics simulations near a vapor-liquid equilibrium state and it decreases as the system becomes a nonequilibrium state. The condensation coefficient of water is nearly identical with that of methanol [Mikami, S., Kobayashi, K., Ota, T., Fujikawa, S., Yano, T., Ichijo, M., 2006. Molecular gas dynamics approaches to interfacial phenomena accompanied with condensation. Exp. Therm. Fluid Sci. 30, 795-800].

Condensation coefficient of water in a weak condensation state

Science.gov (United States)

Kobayashi, Kazumichi; Watanabe, Shunsuke; Yamano, Daigo; Yano, Takeru; Fujikawa, Shigeo

2008-07-01

The condensation coefficient of water at a vapor-liquid interface is determined by combining shock tube experiments and numerical simulations of the Gaussian-BGK Boltzmann equation. The time evolution in thickness of a liquid film, which is formed on the shock tube endwall behind the shock wave reflected at the endwall, is measured with an optical interferometer consisting of the physical beam and the reference one. The reference beam is utilized to eliminate systematic noises from the physical beam. The growth rate of the film is evaluated from the measured time evolution and it is incorporated into the kinetic boundary condition for the Boltzmann equation. From a numerical simulation using the boundary condition, the condensation coefficient of water is uniquely deduced. The results show that, in a condition of weak condensation near a vapor-liquid equilibrium state, the condensation coefficient of water is almost equal to the evaporation coefficient estimated by molecular dynamics simulations near a vapor-liquid equilibrium state and it decreases as the system becomes a nonequilibrium state. The condensation coefficient of water is nearly identical with that of methanol [Mikami, S., Kobayashi, K., Ota, T., Fujikawa, S., Yano, T., Ichijo, M., 2006. Molecular gas dynamics approaches to interfacial phenomena accompanied with condensation. Exp. Therm. Fluid Sci. 30, 795-800].

Experimental and computational analysis of steam condensation in the presence of air and helium

International Nuclear Information System (INIS)

Bucci, M.

2010-01-01

Among the different phenomena expected to occur within nuclear reactor containments during a postulated loss of coolant accident, condensation on containment walls plays a major role, since it represents an important heat sink for evacuating the energy released by the discharge of the primary water. Nevertheless, condensation strongly affects other relevant phenomena, like containment atmosphere mixing, that influences the distribution of non-condensable gases hypothetically delivered in severe accident conditions. In this scenario, the role of condensation is not obvious, since it can locally aid the hydrogen produced by the oxidation of the core claddings to concentrate and reach flammability limits, providing a dangerous effect instead of a positive one. The understanding of condensation in the presence of air and hydrogen is therefore a fundamental task for the safety analyses of reactor containments. This research has been carried out with the aim to contribute to the understanding of these phenomena. A double strategy has been adopted, including complementary experimental and computational activities. Novel data have been made available by the CONAN facility, investigating the effects induced by light non-condensable gases in experimental configurations that were scarcely investigated in past studies. Computational fluid dynamics (CFD) condensation models have been developed and validated. The suitability of helium as a substitute for hydrogen in experimental activities has been investigated by theoretical and computational analyses allowing to establish simple criteria for the scaling of condensation tests in the presence of a light non-condensable gas. (authors)

Hong kong chemical waste treatment facilities: a technology overview

Energy Technology Data Exchange (ETDEWEB)

Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

1994-12-31

The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

Hong kong chemical waste treatment facilities: a technology overview

Energy Technology Data Exchange (ETDEWEB)

Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

1993-12-31

The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

Enhanced Condensation Heat Transfer

Science.gov (United States)

Rose, John Winston

The paper gives some personal observations on various aspects of enhanced condensation heat transfer. The topics discussed are external condensation (horizontal low-finned tubes and wire-wrapped tubes), internal condensation (microfin tubes and microchannels) and Marangoni condensation of binary mixtures.

200 area effluent treatment facility opertaional test report

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document reports the results of the 200 Area Effluent Treatment Facility (200 Area ETF) operational testing activities. These Operational testing activities demonstrated that the functional, operational and design requirements of the 200 Area ETF have been met and identified open items which require retesting

Condensation in a two-phase pool

International Nuclear Information System (INIS)

Duffey, R.B.; Hughes, E.D.

1991-01-01

We consider the case of vapor condensation in a liquid pool, when the heat transfer is controlled by heat losses through the walls. The analysis is based on drift flux theory for phase separation in the pool, and determines the two-phase mixture height for the pool. To our knowledge this is the first analytical treatment of this classic problem that gives an explicit result, previous work having established the result for the evaporative case. From conservation of mass and energy in a one-dimensional steady flow, together with a void relation between the liquid and vapor fluxes, we determine the increase in the mixture level from the base level of the pool. It can be seen that the thermal and hydrodynamic influences are separable. Thus, the thermal influence of the wall heat transfer appears through its effect on the condensing length L*, so that at high condensation rates the pool is all liquid, and at low rates overflows (the level swell or foaming effect). Similarly, the phase separation effect hydrodynamically determines the height via the relative velocity of the mixture to the entering flux. We examine some practical applications of this result to level swell in condensing flows, and also examine some limits in ideal cases

Effect of Mixed Working Fluid Composition on Binary Cycle Condenser Heat Transfer Coefficients

Energy Technology Data Exchange (ETDEWEB)

Dan Wendt; Greg Mines

2011-10-01

Effect of Mixed Working Fluid Composition on Binary Cycle Condenser Heat Transfer Coefficients Dan Wendt, Greg Mines Idaho National Laboratory The use of mixed working fluids in binary power plants can provide significant increases in plant performance, provided the heat exchangers are designed to take advantage of these fluids non-isothermal phase changes. In the 1980's testing was conducted at DOE's Heat Cycle Research Facility (HCRF) where mixtures of different compositions were vaporized at supercritical pressures and then condensed. This testing had focused on using the data collected to verify that Heat Transfer Research Incorporated (HTRI) codes were suitable for the design of heat exchangers that could be used with mixtures. The HCRF data includes mixture compositions varying from 0% to 40% isopentane and condenser tube orientations of 15{sup o}, 60{sup o}, and 90{sup o} from horizontal. Testing was performed over a range of working fluid and cooling fluid conditions. Though the condenser used in this testing was water cooled, the working fluid condensation occurred on the tube-side of the heat exchanger. This tube-side condensation is analogous to that in an air-cooled condenser. Tube-side condensing heat transfer coefficient information gleaned from the HCRF testing is used in this study to assess the suitability of air-cooled condenser designs for use with mixtures. Results of an air-cooled binary plant process model performed with Aspen Plus indicate that that the optimal mixture composition (producing the maximum net power for the scenario considered) is within the range of compositions for which data exist. The HCRF data is used to assess the impact of composition, tube orientation, and process parameters on the condensing heat transfer coefficients. The sensitivity of the condensing coefficients to these factors is evaluated and the suitability of air-cooled condenser designs with mixtures is assessed. This paper summarizes the evaluation

Experimental and theoretical study of reflux condensation

Energy Technology Data Exchange (ETDEWEB)

Bakke, Knut

1997-12-31

This thesis studies the separation of gas mixtures in a reflux condenser. also called a dephlegmator. Reflux condensation is separation of a gas mixture, in reflux flow with condensing liquid, under continuous heat removal. A numerical model of a dephlegmator for binary mixtures was developed. The model may readily be extended to multi-component mixtures, as the solution method is based on a matrix solver. Separation of a binary mixture in a reflux condenser test rig is demonstrated. The test facility contains a single-tube test section that was designed and built as part of the project. Test mixtures of propane and n-butane were used, and a total of 15 experiments are reported. Limited degree of separation was achieved due to limited heat transfer area and narrow boiling point range of the test mixture. The numerical model reproduces the experimental data within reasonable accuracy. Deviation between calculated and measured properties is less than 6% of the measured temperature and less than 5% of the measured flow rate. The model is based on mechanistic models of physical processes and is not calibrated or tuned to fit the experimental data. The numerical model is applied to a number of separation processes. These case studies show that the required heat transfer area increases rapidly with increments in top product composition (light component). Flooding limits the amount of reflux liquid. The dephlegmator is suitable for separation of feed mixtures that are rich in light components. The gliding temperature in the dephlegmation process enables utilization of top product as refrigerant, with subsequent energy saving as a result. 61 refs., 50 figs., 34 tabs.

Low-level wastewater treatment facility process control operational test report

International Nuclear Information System (INIS)

Bergquist, G.G.

1996-01-01

This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances

Evaluation formulas of manpower needs for dismantling of equipment in FUGEN-3. Dismantling process of the condenser removal

International Nuclear Information System (INIS)

Kubota, Shintaro; Izumo, Sari; Usui, Hideo; Kawagoshi, Hiroshi; Koda, Yuya; Nanko, Takashi

2014-07-01

Japan Atomic Energy Agency (JAEA) has been developing the PRODIA code which supports to make decommissioning plan and has been preparing evaluation formulas. Manpower needs for the dismantling of the condenser that had conducted from 2010 to 2012 was analyzed and compared with existing evaluation formulas. Applicability of evaluation formulas for a large scale reactor facility was confirmed in dismantling of the heat insulating materials and reliability of unit productivity factor was improved. The evaluation formula of work for clearance was made in dismantling of pipes and supports. Unit productivity factor of dismantling of feed water heaters which is applicable for a large scale reactor facility was derived. For derivation of unit productivity factor, statistically meaningful data was provided from the dismantling of the condenser. Manpower needs for dismantling of the condenser has positive correlation to the weight of equipment and can be described in linear expression. Reliability of each unit productivity factor will be improved with accumulating actual dismantling data in future. (author)

Modelling of Condensation in Vertical Tubes for Passive Safety System

International Nuclear Information System (INIS)

Papini, D.; Ricotti, M.; Santini, L.; Grgic, D.

2008-01-01

Condensation in vertical tubes plays an important role in the performance of heat exchangers in passive safety systems, widely adopted in next generation reactors. Vertical pipe condensers are implemented in the GE-SBWR1000 Isolation Condenser as well as in the Emergency Heat Removal System (EHRS) of the IRIS reactor. The transient and safety analysis is usually carried out by means of best-estimate, thermalhydraulic codes, as RELAP. Suitable heat transfer correlations are required to duly model the two-phase processes. As far as the condensation process is concerned, RELAP5/MOD3.3 adopts the Nusselt correlation to calculate the heat transfer coefficient in laminar conditions and the Shah correlation for turbulent conditions; the maximum of the predictions from laminar and turbulent regimes is used to calculate the condensation heat transfer coefficient. Shah correlation is generally considered as the best empirical correlation for turbulent annular film condensation, but suitable in proper ranges of the various parameters. Nevertheless, recent investigations have pointed out that its validity is highly questionable for high pressure and large diameter tube applications with water, as should be for the utilization for vertical tube condensers in passive safety systems. Thus, a best-estimate model, based on the theory of film condensation on a plain wall, is proposed. Condensate velocity, expressed in terms of Reynolds number, governs the development of three different regime zones: laminar, laminar wavy and turbulent. The best correlation for each regime (Nusselt's for laminar, Kutateladze's for laminar wavy and Chen's for turbulent) is considered and then implemented in RELAP code. Comparison between the Nusselt-Shah and the proposed model shows substantial differences in heat transfer coefficient prediction. Especially, a trend of increasing value of the heat transfer coefficient with tube abscissa (and quality decreasing) is predicted, when turbulence

Measurement of liquid-liquid equilibria for condensate + glycol and condensate + glycol + water systems

DEFF Research Database (Denmark)

Riaz, Muhammad; Kontogeorgis, Georgios; Stenby, Erling Halfdan

2011-01-01

,2-ethanediol (MEG) + condensate and MEG + water + condensate systems at temperatures from (275 to 323) K at atmospheric pressure. The condensate used in this work is a stabilized natural gas condensate from an offshore field in the North Sea. Compositional analysis of the natural gas condensate was carried out...... by gas chromatography, and detailed separation of individual condensate's components has been carried out. Approximately 85 peaks eluting before nonane were identified by their retention time. Peak areas were converted to mass fraction using 1-heptene as an internal standard. The components were divided...... into boiling range groups from hexane to nonane. Paraffinic (P), naphthenic (N), and aromatic (A) distributions were obtained for the boiling point fractions up to nonane. The average molar mass and the overall density of the condensate were measured experimentally. For the mutual solubility of MEG...

Geothermal energy conversion facility

Energy Technology Data Exchange (ETDEWEB)

Kutscher, C.F.

1997-12-31

With the termination of favorable electricity generation pricing policies, the geothermal industry is exploring ways to improve the efficiency of existing plants and make them more cost-competitive with natural gas. The Geothermal Energy Conversion Facility (GECF) at NREL will allow researchers to study various means for increasing the thermodynamic efficiency of binary cycle geothermal plants. This work has received considerable support from the US geothermal industry and will be done in collaboration with industry members and utilities. The GECF is being constructed on NREL property at the top of South Table Mountain in Golden, Colorado. As shown in Figure 1, it consists of an electrically heated hot water loop that provides heating to a heater/vaporizer in which the working fluid vaporizes at supercritical or subcritical pressures as high as 700 psia. Both an air-cooled and water-cooled condenser will be available for condensing the working fluid. In order to minimize construction costs, available equipment from the similar INEL Heat Cycle Research Facility is being utilized.

Modeling Accessibility of Screening and Treatment Facilities for Older Adults using Transportation Networks.

Science.gov (United States)

Zhang, Qiuyi; Northridge, Mary E; Jin, Zhu; Metcalf, Sara S

2018-04-01

Increased lifespans and population growth have resulted in an older U.S. society that must reckon with the complex oral health needs that arise as adults age. Understanding accessibility to screening and treatment facilities for older adults is necessary in order to provide them with preventive and restorative services. This study uses an agent-based model to examine the accessibility of screening and treatment facilities via transportation networks for older adults living in the neighborhoods of northern Manhattan, New York City. Older adults are simulated as socioeconomically distinct agents who move along a GIS-based transportation network using transportation modes that mediate their access to screening and treatment facilities. This simulation model includes four types of mobile agents as a simplifying assumption: walk, by car, by bus, or by van (i.e., a form of transportation assistance for older adults). These mobile agents follow particular routes: older adults who travel by car, bus, and van follow street roads, whereas pedestrians follow walkways. The model enables the user to focus on one neighborhood at a time for analysis. The spatial dimension of an older adult's accessibility to screening and treatment facilities is simulated through the travel costs (indicated by travel time or distance) incurred in the GIS-based model environment, where lower travel costs to screening and treatment facilities imply better access. This model provides a framework for representing health-seeking behavior that is contextualized by a transportation network in a GIS environment.

Low pressure lithium condensation

International Nuclear Information System (INIS)

Wadkins, R.P.; Oh, C.H.

1985-01-01

A low pressure experiment to evaluate the laminar film condensation coefficients of lithium was conducted. Some thirty-six different heat transfer tests were made at system pressures ranging from 1.3 to 26 Pa. Boiled lithium was condensed on the inside of a 7.6-cm (ID), 409 stainless-steel pipe. Condensed lithium was allowed to reflux back to the pool boiling region below the condensing section. Fourteen chromel/alumel thermocouples were attached in various regions of the condensing section. The thermocouples were initially calibrated with errors of less than one degree Celsius

Excitations of Bose-Einstein condensates at finite temperatures

International Nuclear Information System (INIS)

Rusch, M.

2000-01-01

Recent experimental observations of collective excitations of Bose condensed atomic vapours have stimulated interest in the microscopic description of the dynamics of a Bose-Einstein condensate confined in an external potential. We present a finite temperature field theory for collective excitations of trapped Bose-Einstein condensates and use a finite-temperature linear response formalism, which goes beyond the simple mean-field approximation of the Gross-Pitaevskii equation. The effect of the non-condensed thermal atoms we include using perturbation theory in a quasiparticle basis. This presents a simple scheme to understand the interaction between condensate and non-condensed atoms and enables us to include the effect the condensate has on collision dynamics. At first we limit our treatment to the case of a spatially homogeneous Bose gas. We include the effect of pair and triplet anomalous averages and thus obtain a gapless theory for the excitations of a weakly interacting system, which we can link to well known results for Landau and Beliaev damping rates. A gapless theory for trapped systems with a static thermal component follows straightforwardly. We then investigate finite temperature excitations of a condensate in a spherically symmetric harmonic trap. We avoid approximations to the density of states and thus emphasise finite size aspects of the problem. We show that excitations couple strongly to a restricted number of modes, giving rise to resonance structure in their frequency spectra. Where possible we derive energy shifts and lifetimes of excitations. For one particular mode, the breathing mode, the effects of the discreteness of the system are sufficiently pronounced that the simple picture of an energy shift and width fails. Experiments in spherical traps have recently become feasible and should be able to test our detailed quantitative predictions. (author)

Association Between Treatment at High-Volume Facilities and Improved Overall Survival in Soft Tissue Sarcomas.

Science.gov (United States)

Venigalla, Sriram; Nead, Kevin T; Sebro, Ronnie; Guttmann, David M; Sharma, Sonam; Simone, Charles B; Levin, William P; Wilson, Robert J; Weber, Kristy L; Shabason, Jacob E

2018-03-15

Soft tissue sarcomas (STS) are rare malignancies that require complex multidisciplinary management. Therefore, facilities with high sarcoma case volume may demonstrate superior outcomes. We hypothesized that STS treatment at high-volume (HV) facilities would be associated with improved overall survival (OS). Patients aged ≥18 years with nonmetastatic STS treated with surgery and radiation therapy at a single facility from 2004 through 2013 were identified from the National Cancer Database. Facilities were dichotomized into HV and low-volume (LV) cohorts based on total case volume over the study period. OS was assessed using multivariable Cox regression with propensity score-matching. Patterns of care were assessed using multivariable logistic regression analysis. Of 9025 total patients, 1578 (17%) and 7447 (83%) were treated at HV and LV facilities, respectively. On multivariable analysis, high educational attainment, larger tumor size, higher grade, and negative surgical margins were statistically significantly associated with treatment at HV facilities; conversely, black race and non-metropolitan residence were negative predictors of treatment at HV facilities. On propensity score-matched multivariable analysis, treatment at HV facilities versus LV facilities was associated with improved OS (hazard ratio, 0.87, 95% confidence interval, 0.80-0.95; P = .001). Older age, lack of insurance, greater comorbidity, larger tumor size, higher tumor grade, and positive surgical margins were associated with statistically significantly worse OS. In this observational cohort study using the National Cancer Database, receipt of surgery and radiation therapy at HV facilities was associated with improved OS in patients with STS. Potential sociodemographic disparities limit access to care at HV facilities for certain populations. Our findings highlight the importance of receipt of care at HV facilities for patients with STS and warrant further study into improving access to

SLAC synchronous condenser

International Nuclear Information System (INIS)

Corvin, C.

1995-06-01

A synchronous condenser is a synchronous machine that generates reactive power that leads real power by 90 degrees in phase. The leading reactive power generated by the condenser offsets or cancels the normal lagging reactive power consumed by inductive and nonlinear loads at the accelerator complex. The quality of SLAC's utility power is improved with the addition of the condenser. The inertia of the condenser's 35,000 pound rotor damps and smoothes voltage excursions on two 12 kilovolt master substation buses, improving voltage regulation site wide. The condenser absorbs high frequency transients and noise in effect ''scrubbing'' the electric system power at its primary distribution source. In addition, the condenser produces a substantial savings in power costs. Federal and investor owned utilities that supply electric power to SLAC levy a monthly penalty for lagging reactive power delivered to the site. For the 1993 fiscal year this totaled over $285,000 in added costs for the year. By generating leading reactive power on site, thereby reducing total lagging reactive power requirements, a substantial savings in electric utility bills is achieved. Actual savings of $150,000 or more a year are possible depending on experimental operations

Conditions for maximum isolation of stable condensate during separation in gas-condensate systems

Energy Technology Data Exchange (ETDEWEB)

Trivus, N.A.; Belkina, N.A.

1969-02-01

A thermodynamic analysis is made of the gas-liquid separation process in order to determine the relationship between conditions of maximum stable condensate separation and physico-chemical nature and composition of condensate. The analysis was made by considering the multicomponent gas-condensate fluid produced from Zyrya field as a ternary system, composed of methane, an intermediate component (propane and butane) and a heavy residue, C/sub 6+/. Composition of 5 ternary systems was calculated for a wide variation in separator conditions. At each separator pressure there is maximum condensate production at a certain temperature. This occurs because solubility of condensate components changes with temperature. Results of all calculations are shown graphically. The graphs show conditions of maximum stable condensate separation.

Radioactive Liquid Waste Treatment Facility: Environmental Information Document

Energy Technology Data Exchange (ETDEWEB)

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

1993-11-01

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

Radioactive Liquid Waste Treatment Facility: Environmental Information Document

International Nuclear Information System (INIS)

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

1993-11-01

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

Facilities for treatment of radioactive contaminated water in nuclear power plants

International Nuclear Information System (INIS)

1981-02-01

The standard applies to processes applied in facilities for treatment of radioactive contaminated water in nuclear power plants with LWR- and HTR-type reactors. It does not apply to the treatment of concentrates obtained in the decontamination of water. (orig.) [de

Condensate polishing guidelines for PWR and BWR plants

International Nuclear Information System (INIS)

Robbins, P.; Crinigan, P.; Graham, B.; Kohlmann, R.; Crosby, C.; Seager, J.; Bosold, R.; Gillen, J.; Kristensen, J.; McKeen, A.; Jones, V.; Sawochka, S.; Siegwarth, D.; Keeling, D.; Polidoroff, T.; Morgan, D.; Rickertsen, D.; Dyson, A.; Mills, W.; Coleman, L.

1993-03-01

Under EPRI sponsorship, an industry committee, similar in form and operation to other guideline committees, was created to develop Condensate Polishing Guidelines for both PWR and BWR systems. The committee reviewed the available utility and water treatment industry experience on system design and performance and incorporated operational and state-of-the-art information into document. These guidelines help utilities to optimize present condensate polisher designs as well as be a resource for retrofits or new construction. These guidelines present information that has not previously been presented in any consensus industry document. The committee generated guidelines that cover both deep bed and powdered resin systems as an integral part of the chemistry of PWR and BWR plants. The guidelines are separated into sections that deal with the basis for condensate polishing, system design, resin design and application, data management and performance and management responsibilities

LIQUID EFFLUENT RETENTION FACILITY (LERF) BASIN 42 STUDIES

International Nuclear Information System (INIS)

DUNCAN JB

2004-01-01

This report documents laboratory results obtained under test plan RPP-21533 for samples submitted by the Effluent Treatment Facility (ETF) from the Liquid Effluent Retention Facility (LERF) Basin 42 (Reference 1). The LERF Basin 42 contains process condensate (PC) from the 242-A Evaporator and landfill leachate. The ETF processes one PC campaign approximately every 12 to 18 months. A typical PC campaign volume can range from 1.5 to 2.5 million gallons. During the September 2003 ETF Basin 42 processing campaign, a recurring problem with 'gelatinous buildup' on the outlet filters from 60A-TK-I (surge tank) was observed (Figure 1). This buildup appeared on the filters after the contents of the surge tank were adjusted to a pH of between 5 and 6 using sulfuric acid. Biological activity in the PC feed was suspected to be the cause of the gelatinous material. Due to this buildup, the filters (10 (micro)m CUNO) required daily change out to maintain process throughput

LIQUID EFFLUENT RETENTION FACILITY (LERF) BASIN 42 STUDIES

Energy Technology Data Exchange (ETDEWEB)

DUNCAN JB

2004-10-29

This report documents laboratory results obtained under test plan RPP-21533 for samples submitted by the Effluent Treatment Facility (ETF) from the Liquid Effluent Retention Facility (LERF) Basin 42 (Reference 1). The LERF Basin 42 contains process condensate (PC) from the 242-A Evaporator and landfill leachate. The ETF processes one PC campaign approximately every 12 to 18 months. A typical PC campaign volume can range from 1.5 to 2.5 million gallons. During the September 2003 ETF Basin 42 processing campaign, a recurring problem with 'gelatinous buildup' on the outlet filters from 60A-TK-I (surge tank) was observed (Figure 1). This buildup appeared on the filters after the contents of the surge tank were adjusted to a pH of between 5 and 6 using sulfuric acid. Biological activity in the PC feed was suspected to be the cause of the gelatinous material. Due to this buildup, the filters (10 {micro}m CUNO) required daily change out to maintain process throughput.

First Dutch Consensus of Pain Quality Indicators for Pain Treatment Facilities

NARCIS (Netherlands)

Meij, N. de; Grotel, M. van; Patijn, J.; Weijden, T.T. van der; Kleef, M. van

2016-01-01

BACKGROUND: There is a general consensus about the need to define and improve the quality of pain treatment facilities. Although guidelines and recommendations to improve the quality of pain practice management have been launched, provision of appropriate pain treatment is inconsistent and the

Use of nuclear explosions to create gas condensate storage in the USSR. LLL Treaty Verification Program

International Nuclear Information System (INIS)

Borg, I.Y.

1982-01-01

The Soviet Union has described industrial use of nuclear explosions to produce underground hydrocarbon storage. To examples are in the giant Orenburg gas condensate field. There is good reason to believe that three additional cavities were created in bedded salt in the yet to be fully developed giant Astrakhan gas condensate field in the region of the lower Volga. Although contrary to usual western practice, the cavities are believed to be used to store H 2 S-rich, unstable gas condensate prior to processing in the main gas plants located tens of kilometers from the producing fields. Detonations at Orenburg and Astrakhan preceded plant construction. The use of nuclear explosions at several sites to create underground storage of highly corrosive liquid hydrocarbons suggests that the Soviets consider this time and cost effective. The possible benefits from such a plan include degasification and stabilization of the condensate before final processing, providing storage of condensate during periods of abnormally high natural gas production or during periods when condensate but not gas processing facilities are undergoing maintenance. Judging from information provided by Soviet specialists, the individual cavities have a maximum capacity on the order of 50,000 m 3

MATRIX-VBS Condensing Organic Aerosols in an Aerosol Microphysics Model

Science.gov (United States)

Gao, Chloe Y.; Tsigaridis, Konstas; Bauer, Susanne E.

2015-01-01

The condensation of organic aerosols is represented in a newly developed box-model scheme, where its effect on the growth and composition of particles are examined. We implemented the volatility-basis set (VBS) framework into the aerosol mixing state resolving microphysical scheme Multiconfiguration Aerosol TRacker of mIXing state (MATRIX). This new scheme is unique and advances the representation of organic aerosols in models in that, contrary to the traditional treatment of organic aerosols as non-volatile in most climate models and in the original version of MATRIX, this new scheme treats them as semi-volatile. Such treatment is important because low-volatility organics contribute significantly to the growth of particles. The new scheme includes several classes of semi-volatile organic compounds from the VBS framework that can partition among aerosol populations in MATRIX, thus representing the growth of particles via condensation of low volatility organic vapors. Results from test cases representing Mexico City and a Finish forrest condistions show good representation of the time evolutions of concentration for VBS species in the gas phase and in the condensed particulate phase. Emitted semi-volatile primary organic aerosols evaporate almost completely in the high volatile range, and they condense more efficiently in the low volatility range.

1976 Hanford americium-exposure incident: decontamination and treatment facility

International Nuclear Information System (INIS)

Berry, J.R.; McMurray, B.J.; Jech, J.J.; Breitenstein, B.D.; Quigley, E.J.

1982-01-01

An injured worker, contaminated with over 6 mCi of americium-241, required special treatment and housing for 4 months. This paper is a description of the design and management of the facility in which most of the treatment and housing occurred. The problems associated with contamination control, waste handling, supplies, and radiological concerns during the two-stage transfer of the patient from a controlled situation to his normal living environment are discussed in detail

Differences between U.S. substance abuse treatment facilities that do and do not offer domestic violence services.

Science.gov (United States)

Cohn, Amy; Najavits, Lisa M

2014-04-01

Victimization by and perpetration of domestic violence are associated with co-occurring mental and substance use disorders. This study used data from the National Survey of Substance Abuse Treatment Services to examine differences in organizational factors, treatment approaches offered, and client-level factors among 13,342 substance abuse treatment facilities by whether or not they offered domestic violence services. Only 36% of the facilities offered domestic violence services. Those that offered such services were more likely than those that did not to treat clients with co-occurring disorders. Principal-components analysis reduced eight treatment approaches to two factors: psychosocial services and traditional substance abuse services. Regression models indicated that the frequency with which psychosocial services were offered depended on the percentage of clients with co-occurring disorders who were being treated in the facility and whether or not that facility offered domestic violence services. Specifically, facilities that did not offer domestic violence services and that had a high percentage of clients with co-occurring disorders were more likely to offer psychosocial services than facilities that offered domestic violence services. A larger proportion of facilities offering domestic violence services offered traditional substance abuse treatment services, compared with facilities not offering domestic violence services, but this relationship was not contingent on the percentage of clients with co-occurring disorders at each facility. Improved efforts should be made to tailor treatments to accommodate the links between domestic violence, mental disorders, and substance abuse.

Request for modification of 200 Area effluent treatment facility final delisting

International Nuclear Information System (INIS)

Bowman, R.C.

1998-01-01

A Delisting Petition submitted to the U.S. Environmental Protection Agency in August 1993 addressed effluent to be generated at the 200 Area Effluent Treatment Facility from treating Hanford Facility waste streams. This Delisting Petition requested that 71.9 million liters per year of treated effluent, bearing the designation 'F001' through 'F005', and/or 'F039' that is derived from 'F001' through 'F005' waste, be delisted. On June 13, 1995, the U.S. Environmental Protection Agency published the final rule (Final Delisting), which formally excluded 71.9 million liters per year of 200 Area Effluent Treatment Facility effluent from ''being listed as hazardous wastes'' (60 FR 31115 now promulgated in 40 CFR 261). Given the limited scope, it is necessary to request a modification of the Final Delisting to address the management of a more diverse multi-source leachate (F039) at the 200 Area Effluent Treatment Facility. From past operations and current cleanup activities on the Hanford Facility, a considerable amount of both liquid and solid Resource Conservation and Recovery Act of 1976 regulated mixed waste has been and continues to be generated. Ultimately this waste will be treated as necessary to meet the Resource Conservation and Recovery Act Land Disposal Restrictions. The disposal of this waste will be in Resource Conservation and Recovery Act--compliant permitted lined trenches equipped with leachate collection systems. These operations will result in the generation of what is referred to as multi-source leachate. This newly generated waste will receive the listed waste designation of F039. This waste also must be managed in compliance with the provisions of the Resource Conservation and Recovery Act

Hydrogen peroxide in exhaled breath condensate: A clinical study

Directory of Open Access Journals (Sweden)

C Nagaraja

2012-01-01

Full Text Available Objectives: To study the ongoing inflammatory process of lung in healthy individuals with risk factors and comparing with that of a known diseased condition. To study the inflammatory response to treatment. Background: Morbidity and mortality of respiratory diseases are raising in trend due to increased smokers, urbanization and air pollution, the diagnosis of these conditions during early stage and management can improve patient′s lifestyle and morbidity. Materials and Methods: One hundred subjects were studied from July 2010 to September 2010; the level of hydrogen peroxide concentration in exhaled breath condensate was measured using Ecocheck. Results: Of the 100 subjects studied, 23 were healthy individuals with risk factors (smoking, exposure to air pollution, and urbanization; the values of hydrogen peroxide in smokers were 200-2220 nmol/l and in non-smokers 340-760 nmol/l. In people residing in rural areas values were 20-140 nmol/l in non-smokers and 180 nmol/l in smokers. In chronic obstructive pulmonary disease cases, during acute exacerbations values were 540-3040 nmol/l and 240-480 nmol/l following treatment. In acute exacerbations of bronchial asthma, values were 400-1140 nmol/l and 100-320 nmol/l following treatment. In cases of bronchiectasis, values were 300-340 nmol/l and 200-280 nmol/l following treatment. In diagnosed pneumonia cases values were 1060-11800 nmol/l and 540-700 nmol/l following treatment. In interstitial lung diseases, values ranged from 220-720 nmol/l and 210-510 nmol/l following treatment. Conclusion: Exhaled breath condensate provides a non-invasive means of sampling the lower respiratory tract. Collection of exhaled breath condensate might be useful to detect the oxidative destruction of the lung as well as early inflammation of the airways in a healthy individual with risk factors and comparing the inflammatory response to treatment.

FY-1981 project status for the Transuranic Waste Treatment Facility

International Nuclear Information System (INIS)

Benedetti, R.L.; Tait, T.D.

1981-11-01

The primary objective of the Transuranic Waste Treatment Facility (TWTF) Project is to provide a facility to process low-level transuranic waste stored at the Idaho National Engineering Laboratory (INEL) into a form acceptable for disposal at the Waste Isolation Pilot Plant. This report provides brief summary descriptions of the project objectives and background, project status through FY-1981, planned activities for FY-1982, and the EG and G TWTF Project office position on processing INEL transuranic waste

Purification method for condensate

International Nuclear Information System (INIS)

Shimoda, Akiyoshi.

1996-01-01

Condensates generated in secondary coolant circuits of a PWR type reactor are filtered using a hollow thread separation membranes comprising aromatic polyether ketone. Preferably, condensates after passing through a turbine are filtered at a place between a condensator and a steam generator at high temperature as close as a temperature of the steam generator. As the hollow thread membrane, partially crystalline membrane comprising aromatic polyether ketone is used. When it is used at high temperature, the crystallinity is preferably not less than 15wt%. Since a hollow thread membrane comprising the aromatic polyether ketone of excellent heat resistance is used, it can filter and purify the condensates at not lower than 70degC. Accordingly, impurities such as colloidal iron can be removed from the condensates, and the precipitation of cruds in the condensates to a steam generator and a turbine can be suppressed. (I.N.)

On the occurrence and detectability of Bose-Einstein condensation in helium white dwarfs

International Nuclear Information System (INIS)

Benvenuto, O.G.; Vito, M.A. De

2011-01-01

It has been recently proposed that helium white dwarfs may provide promising conditions for the occurrence of the Bose-Einstein condensation. The argument supporting this expectation is that in some conditions attained in the core of these objects, the typical De Broglie wavelength associated with helium nuclei is of the order of the mean distance between neighboring nuclei. In these conditions the system should depart from classical behavior showing quantum effects. As helium nuclei are bosons, they are expected to condense. In order to explore the possibility of detecting the Bose-Einstein condensation in the evolution of helium white dwarfs we have computed a set of models for a variety of stellar masses and values of the condensation temperature. We do not perform a detailed treatment of the condensation process but mimic it by suppressing the nuclei contribution to the equation of state by applying an adequate function. As the cooling of white dwarfs depends on average properties of the whole stellar interior, this procedure should be suitable for exploring the departure of the cooling process from that predicted by the standard treatment. We find that the Bose-Einstein condensation has noticeable, but not dramatic effects on the cooling process only for the most massive white dwarfs compatible with a helium dominated interior ( ≈ 0.50M s un) and very low luminosities (say, Log(L/L s un) < −4.0). These facts lead us to conclude that it seems extremely difficult to find observable signals of the Bose-Einstein condensation. Recently, it has been suggested that the population of helium white dwarfs detected in the globular cluster NGC 6397 is a good candidate for detecting signals of the Bose-Einstein condensation. We find that these stars have masses too low and are too bright to have an already condensed interior

Simple Simulations of DNA Condensation

Energy Technology Data Exchange (ETDEWEB)

STEVENS,MARK J.

2000-07-12

Molecular dynamics simulations of a simple, bead-spring model of semiflexible polyelectrolytes such as DNA are performed. All charges are explicitly treated. Starting from extended, noncondensed conformations, condensed structures form in the simulations with tetravalent or trivalent counterions. No condensates form or are stable for divalent counterions. The mechanism by which condensates form is described. Briefly, condensation occurs because electrostatic interactions dominate entropy, and the favored Coulombic structure is a charge ordered state. Condensation is a generic phenomena and occurs for a variety of polyelectrolyte parameters. Toroids and rods are the condensate structures. Toroids form preferentially when the molecular stiffness is sufficiently strong.

Federal Facilities Compliance Act, Conceptual Site Treatment Plan. Part 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-10-29

This Conceptual Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed in this document include: general discussion of the plan, including the purpose and scope; technical aspects of preparing plans, including the rationale behind the treatability groupings and a discussion of characterization issues; treatment technology needs and treatment options for specific waste streams; low-level mixed waste options; TRU waste options; and future waste generation from restoration activities.

Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

International Nuclear Information System (INIS)

Ranek, N.L.; Coalgate, J.L.

1995-01-01

The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process

Radiation protection -Operation of chemical wastewater treatment facility

International Nuclear Information System (INIS)

Lee, M. J.; Lim, M. H.; Ahn, S. S.; Jeong, Y. S.

1996-12-01

The wastewater and sewage treatment facility have been operated. From the results of operation, it was confirmed that the quality of treated wastewater was 1/5 or 1/10 lower than that of regulation of law for environmental conservation. The quality of treated sewage has been maintained to 70% of regulation of law for environmental conservation. (author). 14 tabs., 8 figs

New Czechoslovak detector of leaking condenser tubes usable in both shutdown and reduced output operation of power unit

International Nuclear Information System (INIS)

Matal, O.; Klinga, J.; Varvarovsky, F.; Zachar, J.; Fratric, D.

1986-01-01

The main reason for penetration of undesirable admixtures from cooling water in the condensate is the inleakage of steam turbine condensers. Briefly assessed are the means and methods of detecting and locating condenser leaks used in the world and in power facilities in Czechoslovakia. Equipment was developed based on measuring the difference between the pressure in a temporarily closed condenser tube and ambient pressure, for leak testing of condenser tubes during operation and during shutdown of WWER-440 units. Two types of the equipment were tested in practice. Type VUEZ-PHN 85P meets the requirements of objective leak tests and those of leak location in condenser tubes and of leak detection in tube expansion in the tube plates of WWER-440 unit condensers, this as concerns sensitivity, the objectivity of results, the cost of tests, and minimal losses of power during the test. Type VUEZ-PHN 85P can be used for leak location in all tube type heat exchangers with access to tube outlets in which under- or overpressure can be achieved in the space between the tubes relative to ambient pressure during the test. (Z.M.) 5 figs., 4 tabs., 11 refs

Condensation shocks in high momentum two-phase flows in condensing injectors

International Nuclear Information System (INIS)

Anand, G.; Christensen, R.N.

1993-01-01

This study presents a phenomenological and mathematical model of condensation shocks in high momentum two-phase flows in condensing injectors. The characteristics of the shock were related to the mode of vapor bubble collapse. Using cavitation terminology, the bubble collapse can be classified as inertially controlled or thermally controlled. Inertial bubble collapse occurs rapidly whereas, a thermally controlled collapse results in a significantly longer collapse time. The interdependence between the bubble collapse mode and the momentum and pressure of the flow, was analyzed in this study. For low-temperature-high-velocity flows a steep pressure rise with complete condensation was obtained. For a high-temperature-low velocity flow with noncondensables, low pressure recovery with incomplete condensation was observed. These trends are in agreement with previous experimental observations

5. International conference on materials science and condensed matter physics and symposium 'Electrical methods of materials treatment'. Abstracts

International Nuclear Information System (INIS)

2010-09-01

This book includes abstracts of the communications presented at the 5th International Conference on Materials Science and Condensed-Matter Physics and at the Symposium dedicated to the 100th anniversary of academician Boris Lazarenko, the prominent scientist and inventor, the first director of the Institute of Applied Physics of the Academy of Sciences of Moldova. The abstracts presented in the book cover a vast range of subjects, such as: advanced materials and fabrication processes; methods of crystal growth, post-growth technological processes, doping and implantation, fabrication of solid state structures; defect engineering, engineering of molecular assembly; methods of nanostructures and nano materials fabrication and characterization; quantum wells and superlattices; nano composite, nanowires and nano dots; fullerenes and nano tubes, molecular materials, meso- and nano electronics; methods of material and structure characterization; structure and mechanical characterization; optical, electrical, magnetic and superconductor properties, transport processes, nonlinear phenomena, size and interface effects; advances in condensed matter theory; theory of low dimensional systems; modelling of materials and structure properties; development of theoretical methods of solid-state characterization; phase transition; advanced quantum physics for nano systems; device modelling and simulation, device structures and elements; micro- and optoelectronics; photonics; microsensors and micro electro-mechanical systems; microsystems; degradation and reliability, solid-state device design; theory and advanced technologies of electro-physico-chemical and combined methods of materials machining and treatment, including modification of surfaces; theory and advanced technologies of using electric fields, currents and discharges so as to intensify heat mass-transfer, to raise the efficiency of treatment of materials, of biological preparations and foodstuff; modern equipment for

Methodology for Determining Increases in Radionuclide Inventories for the Effluent Treatment Facility Process

International Nuclear Information System (INIS)

Blanchard, A.

1998-01-01

A study is currently underway to determine if the Effluent Treatment Facility can be downgraded from a Hazard Category 3 facility to a Radiological Facility per DOE STD-1027-92. This technical report provides a methodology to determine and monitor increases in the radionuclide inventories of the ETF process columns. It also provides guidelines to ensure that other potential increases to the ETF radionuclide inventory are evaluated as required to ensure that the ETF remains a Radiological Facility

Condensation in complex geometries

International Nuclear Information System (INIS)

Lauro, F.

1975-01-01

A mathematical evaluation of the condensation exchange coefficient can only succeds for well specified cases: small upright or inclined plates, horizontal tubes, small height vertical tubes. Among the main hypotheses accounted for this mathematical development in the case of the condensate, a laminar flow and uniform surface temperature are always considered. In practice certain shapes of surfaces significantly increase the heat transfer during the vapor condensation on a surface wet by the condensate. Such surfaces are rough surfaces such as the condensate is submitted to surface tension effects, negligeable for plane or large curvature surfaces, and the nature of the material may play an important role (temperature gradients). Results from tests on tubes with special shapes, performed in France or out of France, are given [fr

Sedimentary condensation and authigenesis

Science.gov (United States)

Föllmi, Karl

2016-04-01

Most marine authigenic minerals form in sediments, which are subjected to condensation. Condensation processes lead to the formation of well individualized, extremely thin ( 100ky), and which experienced authigenesis and the precipitation of glaucony, verdine, phosphate, iron and manganese oxyhydroxides, iron sulfide, carbonate and/or silica. They usually show complex internal stratigraphies, which result from an interplay of sediment accumulation, halts in sedimentation, sediment winnowing, erosion, reworking and bypass. They may include amalgamated faunas of different origin and age. Hardgrounds may be part of condensed beds and may embody strongly condensed beds by themselves. Sedimentary condensation is the result of a hydrodynamically active depositional regime, in which sediment accumulation, winnowing, erosion, reworking and bypass are processes, which alternate as a function of changes in the location and intensity of currents, and/or as the result of episodic high-energy events engendered by storms and gravity flow. Sedimentary condensation has been and still is a widespread phenomenon in past and present-day oceans. The present-day distribution of glaucony and verdine-rich sediments on shelves and upper slopes, phosphate-rich sediments and phosphorite on outer shelves and upper slopes, ferromanganese crusts on slopes, seamounts and submarine plateaus, and ferromanganese nodules on abyssal seafloors is a good indication of the importance of condensation processes today. In the past, we may add the occurrence of oolitic ironstone, carbonate hardgrounds, and eventually also silica layers in banded iron formations as indicators of the importance of condensation processes. Besides their economic value, condensed sediments are useful both as a carrier of geochemical proxies of paleoceanographic and paleoenvironmental change, as well as the product of episodes of paleoceanographic and paleoenvironmental change themselves.

URAM-2 Cryogenic Irradiation Facility

CERN Document Server

Shabalin, E P; Kulikov, S A; Kulagin, E N; Melihov, V V; Belyakov, A A; Golovanov, L B; Borzunov, Yu T; Konstantinov, V I; Androsov, A V

2002-01-01

The URAM-2 irradiation facility has been built and mounted at the channel No. 3 of the IBR-2 reactor. It was constructed for study of radiolysis effects by fast neutron irradiation in some suitable for effective cold neutron production materials (namely: solid methane, methane hydrate, water ice, etc.). The facility cooling system is based on using liquid helium as a coolant material. The original charging block of the rig allows the samples to be loaded by condensing gas into irradiation cavity or by charging beads of ice prepared before. Preliminary tests for each facility block and assembling them at the working position were carried out. Use of the facility for study accumulation of chemical energy under irradiation at low temperature in materials mentioned above and its spontaneous release was started.

Analysis of the suitability of DOE facilities for treatment of commercial low-level radioactive mixed waste

International Nuclear Information System (INIS)

1996-02-01

This report evaluates the capabilities of the United States Department of Energy's (DOE's) existing and proposed facilities to treat 52 commercially generated low-level radioactive mixed (LLMW) waste streams that were previously identified as being difficult-to-treat using commercial treatment capabilities. The evaluation was performed by comparing the waste matrix and hazardous waste codes for the commercial LLMW streams with the waste acceptance criteria of the treatment facilities, as identified in the following DOE databases: Mixed Waste Inventory Report, Site Treatment Plan, and Waste Stream and Technology Data System. DOE facility personnel also reviewed the list of 52 commercially generated LLMW streams and provided their opinion on whether the wastes were technically acceptable at their facilities, setting aside possible administrative barriers. The evaluation tentatively concludes that the DOE is likely to have at least one treatment facility (either existing or planned) that is technically compatible for most of these difficult-to-treat commercially generated LLMW streams. This conclusion is tempered, however, by the limited amount of data available on the commercially generated LLMW streams, by the preliminary stage of planning for some of the proposed DOE treatment facilities, and by the need to comply with environmental statutes such as the Clean Air Act

Mixed convection heat transfer between a steam/non-condensable gas mixture and an inclined finned tube bundle

Energy Technology Data Exchange (ETDEWEB)

De Cachard, F.; Lompersky, S.; Monauni, G.R. [Paul Scherrer Institute, Villigen (Switzerland). Thermal Hydraulic Lab.

1999-07-01

An experimental and analytical program was performed at PSI (Paul Scherrer Institute) to study the performance of a finned-tube condenser in the presence of non-condensable gases at low gas mass fluxes. The model developed for this application includes mixed convection heat transfer between the vapour/non-condensable mixture and the finned tubes, heat conduction through the fins and tubes, and evaporative heat transfer inside the tubes. On the gas, heat transfer correlations are used, and the condensation rate is calculated using the heat/mass transfer analogy. A combination of various available correlations for forced convection in staggered finned tube bundles is used, together with a correction accounting for superimposed natural convection. For the condensate heat transfer resistance, the beatty and Katz model for gravity driven liquid films on the tubes is used. The fine efficiency is accounted for using classical iterative calculations. Evaporative heat transfer inside the tubes is predicted using the Chen correlation. The finned tube condenser model has been assessed against data obtained at the PSI LINX facility with two test condensers. For the 62 LINX experiments performed, the model predictions are very good, i.e., less then 10% standard deviation between experimental and predicted results.

Request for modification of 200 Area effluent treatment facility final delisting

Energy Technology Data Exchange (ETDEWEB)

BOWMAN, R.C.

1998-11-19

A Delisting Petition submitted to the U.S. Environmental Protection Agency in August 1993 addressed effluent to be generated at the 200 Area Effluent Treatment Facility from treating Hanford Facility waste streams. This Delisting Petition requested that 71.9 million liters per year of treated effluent, bearing the designation 'F001' through 'F005', and/or 'F039' that is derived from 'F001' through 'F005' waste, be delisted. On June 13, 1995, the U.S. Environmental Protection Agency published the final rule (Final Delisting), which formally excluded 71.9 million liters per year of 200 Area Effluent Treatment Facility effluent from ''being listed as hazardous wastes'' (60 FR 31115 now promulgated in 40 CFR 261). Given the limited scope, it is necessary to request a modification of the Final Delisting to address the management of a more diverse multi-source leachate (F039) at the 200 Area Effluent Treatment Facility. From past operations and current cleanup activities on the Hanford Facility, a considerable amount of both liquid and solid Resource Conservation and Recovery Act of 1976 regulated mixed waste has been and continues to be generated. Ultimately this waste will be treated as necessary to meet the Resource Conservation and Recovery Act Land Disposal Restrictions. The disposal of this waste will be in Resource Conservation and Recovery Act--compliant permitted lined trenches equipped with leachate collection systems. These operations will result in the generation of what is referred to as multi-source leachate. This newly generated waste will receive the listed waste designation of F039. This waste also must be managed in compliance with the provisions of the Resource Conservation and Recovery Act.

3D Imaging of Water-Drop Condensation on Hydrophobic and Hydrophilic Lubricant-Impregnated Surfaces

Science.gov (United States)

Kajiya, Tadashi; Schellenberger, Frank; Papadopoulos, Periklis; Vollmer, Doris; Butt, Hans-Jürgen

2016-04-01

Condensation of water from the atmosphere on a solid surface is an ubiquitous phenomenon in nature and has diverse technological applications, e.g. in heat and mass transfer. We investigated the condensation kinetics of water drops on a lubricant-impregnated surface, i.e., a micropillar array impregnated with a non-volatile ionic liquid. Growing and coalescing drops were imaged in 3D using a laser scanning confocal microscope equipped with a temperature and humidity control. Different stages of condensation can be discriminated. On a lubricant-impregnated hydrophobic micropillar array these are: (1) Nucleation on the lubricant surface. (2) Regular alignment of water drops between micropillars and formation of a three-phase contact line on a bottom of the substrate. (3) Deformation and bridging by coalescence which eventually leads to a detachment of the drops from the bottom substrate. The drop-substrate contact does not result in breakdown of the slippery behaviour. Contrary, on a lubricant-impregnated hydrophilic micropillar array, the condensed water drops replace the lubricant. Consequently, the surface loses its slippery property. Our results demonstrate that a Wenzel-like to Cassie transition, required to maintain the facile removal of condensed water drops, can be induced by well-chosen surface hydrophobicity.

Modelling of blowdown of steam in the pressurized PPOOLEX facility

Energy Technology Data Exchange (ETDEWEB)

Paettikangas, T.; Niemi, J.; Timperi, A. (VTT Technical Research Centre of Finland (Finland))

2009-12-15

PPOOLEX experiment WLL-04-02 on condensation of vapour is studied with CFD simulations. Wall condensation model has been adapted to an Euler-Euler multiphase model of the Fluent CFD code for this purpose. In addition, a simple direct-contact condensation model has also been included in the code. The main focus of the CFD modelling work was on modelling condensation in the drywell. The amount of condensation found in the CFD calculation was in fair agreement with the experiment. The present simulation was so short that the gas flowing into the wetwell contained significant amount of air. The mole fraction of vapour at the outlet of the vent pipe had the maximum value of about 0.3. Therefore, the noncondensable gas strongly affected the direct-contact condensation in the water pool. Much longer simulations are needed in order to study jugging and condensation oscillations. FSI calculations of the experiments were performed by using the Star-CD, ABAQUS and MpCCI codes. An approximate method that makes possible numerically stable FSI calculations for the experimental facilities was used. The method is based on linear perturbation method which necessitates small structural deformations. The calculations showed that FSI has to be taken into account for the POOLEX facility which has relatively light structures. A way for determining the pressure source for the acoustic model from pressure measured at the pool bottom was also examined. Separation of the pressure component due to wall motion from the blowdown load was attempted by conducting a Fourier analysis on the measured displacement signal. The study showed that in practise sufficiently accurate acceleration signal cannot be obtained this way because the transformed signal gets easily out of phase. A measurement system was proposed which could be used for determining the pressure fluctuations. (author)

Modelling of blowdown of steam in the pressurized PPOOLEX facility

International Nuclear Information System (INIS)

Paettikangas, T.; Niemi, J.; Timperi, A.

2009-12-01

PPOOLEX experiment WLL-04-02 on condensation of vapour is studied with CFD simulations. Wall condensation model has been adapted to an Euler-Euler multiphase model of the Fluent CFD code for this purpose. In addition, a simple direct-contact condensation model has also been included in the code. The main focus of the CFD modelling work was on modelling condensation in the drywell. The amount of condensation found in the CFD calculation was in fair agreement with the experiment. The present simulation was so short that the gas flowing into the wetwell contained significant amount of air. The mole fraction of vapour at the outlet of the vent pipe had the maximum value of about 0.3. Therefore, the noncondensable gas strongly affected the direct-contact condensation in the water pool. Much longer simulations are needed in order to study jugging and condensation oscillations. FSI calculations of the experiments were performed by using the Star-CD, ABAQUS and MpCCI codes. An approximate method that makes possible numerically stable FSI calculations for the experimental facilities was used. The method is based on linear perturbation method which necessitates small structural deformations. The calculations showed that FSI has to be taken into account for the POOLEX facility which has relatively light structures. A way for determining the pressure source for the acoustic model from pressure measured at the pool bottom was also examined. Separation of the pressure component due to wall motion from the blowdown load was attempted by conducting a Fourier analysis on the measured displacement signal. The study showed that in practise sufficiently accurate acceleration signal cannot be obtained this way because the transformed signal gets easily out of phase. A measurement system was proposed which could be used for determining the pressure fluctuations. (author)

Heat transfer performance of condenser tubes in an MSF desalination system

International Nuclear Information System (INIS)

Galal, T.; Kalendar, A.; Al Saftawi, A.; Zedan, M.

2010-01-01

The present research examines the amount of condensed fresh water off the outer-side surface of heat exchangers in an MSF system. The quantitative modeling of condensed water on the outer surface of comparable tubes, enhanced and plain, in a simulated MSF technique is investigated. An adapted simulation design on a test-rig facility, accounting for the condenser tubing in actual industrial desalination plate-form, is used with corrugated and smooth aluminum-brass material tubes 1100mm long and 23mm bore. A single phase flow of authentic brine water that typifies real fouling is utilized to simulate the actual environmental life of a multi-stage flashing desalination system, with coolant flow velocity 0.1 m/s in the two delineated types of condenser tubing. It is demonstrated that the condensate water amount from the specified enhanced tube is about 1.22 times the condensate water amount from the smooth tube, adaptive for 140 running hours under deliberated constrains. The topic covers a comparative analysis of thermal performance. Comparing results with fresh water confirm the effect of fouling on significantly lowering the value of the overall heat transfer coefficient versus time. Fouling resistance R f is reported with the critical coolant flow speed of 0.1 m/s. Comparison between the fouling resistance for both smooth and corrugated tubes versus time is performed. The fouling thermal resistance of the corrugated tube is 0.56 of the fouling thermal resistance of the smooth tube after140 running hours of the experiment are concluded. Overall, in the case of real brine, results prove that heat performance for the corrugated tube is superior to the plain tube over the studied time period (140 hrs) for the chosen range of flow speeds

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Vault design, run-on/run-off control design, and asphalt compatibility with 90-degree celsius double-shell slurry feed

Effect of pool turbulence on direct contact condensation at a steam/water interface

International Nuclear Information System (INIS)

Jackson, J.D.; Zhao, C.L.; Doerffer, S.; Byrne, J.E.; Falaki, H.

2000-01-01

Measurements of direct contact condensation beat transfer have been made for the case where the process takes place at the horizontal interface between saturated steam and a pool of water in a vertical cylindrical test section. A submerged vertical jet of subcooled water was injected upwards on the axis to promote the condensation and water was withdrawn at the same rate from the bottom of the pool. In conjunction with the above study, measurements of the turbulent velocity fluctuations just below a free surface produced by the injection of a vertical submerged jet have been measured using hot film anemometry on an isothermal air-water test facility of similar geometry for similar flow conditions at ambient temperature. A correlation is proposed in terms of a Stanton number based on turbulent velocity fluctuation near the interface on the liquid-side. Our results are in good agreement with those of others for similar configurations when compared in terms of condensation Stanton number. (author)

An Effective Web Presence for Substance Abuse Treatment Facilities.

Science.gov (United States)

Link, Thomas W; Hefner, Jennifer L; Ford, Eric W; Huerta, Timothy R

2016-01-01

Website development for health care has only been prevalent in the last two and a half decades. The first websites were electronic versions of brochures providing hardly any interaction with the consumer or potential consumer. The percentage of consumers that use the internet during the decision-making process for health care providers continues to rise. As a result, the websites of health care providers are becoming more of a representation of the facility and creating an organizational image rather than a brochure-like informational page. The purpose of this study was to analyze substance abuse treatment center's websites in the State of California with the goal of informing the management of substance abuse centers regarding an effective and inexpensive means to closing the marketing gaps in the industry. This brief research report presents the results of employing an automated web-crawler to assess website quality along five dimensions: accessibility, content, marketing, technology, and usability score. The sample mean scores for all dimensions were between 4 and 6 on a 10-point scale. On average larger facilities had higher quality websites. The low mean scores on these dimensions indicate that that substance abuse centers have significant room for improvement of their website's. Efficiently spending marketing funds to increase the effectiveness of a treatment center's website can be a low cost way for even small facilities to increase market competitiveness.

Possibility of removing condensate and scattered oil from gas-condensate field during bed flooding

Energy Technology Data Exchange (ETDEWEB)

Belkina, N.A.; Yagubov, M.S.

1984-01-01

The problem is set of evaluating the possible removal from the bed of scattered oil and condensate during flooding of the bed. For this purpose, an experimental study was made of the displacement by water from the porous medium of the oil and condensate saturating it. The obtained experimental results permit evaluation of the possible removal from the gas-condensate bed of scattered oil and condensate during flooding of the bed.

Research progress of control of condensate depression for condenser

Science.gov (United States)

Liu, Ying; Liang, Run; Li, Fengyu

2017-08-01

It is introduced that significance and structure of the condensate depression control system. In accordance with controller devised procedure, we analyze and elaborate how to construct the lumped parameter and dynamic mathematical model which possesses distinct physics significance. Neural network model being called black-box model is also introduced. We analyze and contrast the control technique of condensate depression as conventional PI control, fuzzy PI control and fuzzy control. It is indicated that if the controller of condensate depression were devised inappropriate, while the steam discharged of turbine varying by a large margin, would result in the rotation rate of cooling water circulating pump accelerating at a great lick even to trigger the galloping danger which is less impressive for the units operating safely.

Universal Themes of Bose-Einstein Condensation

Science.gov (United States)

Proukakis, Nick P.; Snoke, David W.; Littlewood, Peter B.

2017-04-01

Foreword; List of contributors; Preface; Part I. Introduction: 1. Universality and Bose-Einstein condensation: perspectives on recent work D. W. Snoke, N. P. Proukakis, T. Giamarchi and P. B. Littlewood; 2. A history of Bose-Einstein condensation of atomic hydrogen T. Greytak and D. Kleppner; 3. Twenty years of atomic quantum gases: 1995-2015 W. Ketterle; 4. Introduction to polariton condensation P. B. Littlewood and A. Edelman; Part II. General Topics: Editorial notes; 5. The question of spontaneous symmetry breaking in condensates D. W. Snoke and A. J. Daley; 6. Effects of interactions on Bose-Einstein condensation R. P. Smith; 7. Formation of Bose-Einstein condensates M. J. Davis, T. M. Wright, T. Gasenzer, S. A. Gardiner and N. P. Proukakis; 8. Quenches, relaxation and pre-thermalization in an isolated quantum system T. Langen and J. Schmiedmayer; 9. Ultracold gases with intrinsic scale invariance C. Chin; 10. Berezinskii-Kosterlitz-Thouless phase of a driven-dissipative condensate N. Y. Kim, W. H. Nitsche and Y. Yamamoto; 11. Superfluidity and phase correlations of driven dissipative condensates J. Keeling, L. M. Sieberer, E. Altman, L. Chen, S. Diehl and J. Toner; 12. BEC to BCS crossover from superconductors to polaritons A. Edelman and P. B. Littlewood; Part III. Condensates in Atomic Physics: Editorial notes; 13. Probing and controlling strongly correlated quantum many-body systems using ultracold quantum gases I. Bloch; 14. Preparing and probing chern bands with cold atoms N. Goldman, N. R. Cooper and J. Dalibard; 15. Bose-Einstein condensates in artificial gauge fields L. J. LeBlanc and I. B. Spielman; 16. Second sound in ultracold atomic gases L. Pitaevskii and S. Stringari; 17. Quantum turbulence in atomic Bose-Einstein condensates N. G. Parker, A. J. Allen, C. F. Barenghi and N. P. Proukakis; 18. Spinor-dipolar aspects of Bose-Einstein condensation M. Ueda; Part IV. Condensates in Condensed Matter Physics: Editorial notes; 19. Bose

Assessment of TRACE Condensation Model Against Reflux Condensation Tests with Noncondensable Gases

Energy Technology Data Exchange (ETDEWEB)

Lee, Kyung Won; Cheong, Ae Ju; Shin, Andong; Suh, Nam Duk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

The TRACE is the latest in a series of advanced, best-estimated reactor systems code developed by U.S. Nuclear Regulatory Commission for analyzing transient and steady-state neutronic-thermal-hydraulic behavior in light water reactors. This special model is expected to replace the default model in a future code release after sufficient testing has been completed. This study assesses the special condensation model of TRACE 5.0-patch4 against the counter-current flow configuration. For this purpose, the predicted results of special model are compared to the experimental and to those of default model. The KAST reflux condensation test with NC gases are used in this assessment. We assessed the special model for film condensation of TRACE 5.0-patch4 against the data of the reflux condensation test in the presence of NC gases. The special condensation model of TRACE provides a reasonable estimate of HTC with good agreement at the low inlet steam flow rate.

Assessment of TRACE Condensation Model Against Reflux Condensation Tests with Noncondensable Gases

International Nuclear Information System (INIS)

Lee, Kyung Won; Cheong, Ae Ju; Shin, Andong; Suh, Nam Duk

2015-01-01

The TRACE is the latest in a series of advanced, best-estimated reactor systems code developed by U.S. Nuclear Regulatory Commission for analyzing transient and steady-state neutronic-thermal-hydraulic behavior in light water reactors. This special model is expected to replace the default model in a future code release after sufficient testing has been completed. This study assesses the special condensation model of TRACE 5.0-patch4 against the counter-current flow configuration. For this purpose, the predicted results of special model are compared to the experimental and to those of default model. The KAST reflux condensation test with NC gases are used in this assessment. We assessed the special model for film condensation of TRACE 5.0-patch4 against the data of the reflux condensation test in the presence of NC gases. The special condensation model of TRACE provides a reasonable estimate of HTC with good agreement at the low inlet steam flow rate

Analysis of glycerin waste in A-Area sanitary treatment facility material

International Nuclear Information System (INIS)

1995-01-01

TNX has a large supply of 55 gallon drums containing pure glycerin and glycerin with additives. The glycerin drums were procured to simulate the glass stream in a pilot-scale melter process at TNX. Since the glycerin was not used for this process, TNX is looking at disposing the material in a sanitary waste treatment facility onsite. The effect of adding the contents of the drums to sewage bacteria was tested. A drum of pure glycerin and a drum of glycerin mixed with lithium chloride were tested. The test consisted of mixing sanitary sludge material with the glycerin material. The purpose of the test was to determine if the glycerin impacted the aerobic bacterial population. The bacterial densities were determined by taking samples from the sludge/glycerin mixtures and using aerobic plate count methods. The total organic carbon (TOC) levels were measured before and after testing. The results indicate that the cell density of the aerobic bacteria increased with the addition of glycerin and the glycerin mixture and the TOC removal rate was different for all tests. Disposal of glycerin in the wastewater treatment facilities should pose no problems. Additional testing and analysis of the mixed samples should be done before its disposal in a waste water treatment facility

A pulsed neutron facility for condensed matter research

International Nuclear Information System (INIS)

Hobbis, L.C.W.; Rees, G.H.; Stirling, G.C.

1977-06-01

The scientific and technical basis of the project is presented, as follows: broad synopsis of the proposal for a spallation neutron facility; description of neutron scattering and current work in the UK; scientific applications of the Spallation Neutron Source; discussion of various types of neutron sources; outline description of the SNS and its neutron performance parameters; appendix dealing in more detail with utilization (solid state physics, fluids and amorphous solids, structure determination, molecular and biological sciences); appendix dealing in more detail with the project design (800 MeV synchrotron, target station, shielding, radioactivity and radiation damage, utilization, overall programme). (U.K.)

An Experimental Study of the Dropwise Condensation on Physically Processed Surface

International Nuclear Information System (INIS)

Choi, Jaeyoung; Chang, Soonheung; Watanabe, N.; Sambuichi, T.; Shiota, D.; Aritomi, M.

2013-01-01

Recent research by Kawakubo et al. derived empirical condensation heat transfer correlation suitable for wider range of operating condition in presence of non-condensable gas. However, their proposals of PCCS are focused on plane tube surface. To design better PCCS heat exchanger with high heat transfer coefficient new treatment on condensation surface can be considered in order to maintain dropwise condensation, the heat transfer coefficient of which has an order of magnitude larger than those of film condensation. Advanced research measure dropwise condensation heat transfer coefficient of Au and Cr coated surface based on number of droplet and droplet growth rate. However, coated surface is not desirable in power plant due to its duration of few years. On the other hand, physical processing (micro holes and patterns) on stainless steel and titanium surface is expected to perform better heat transfer, also is durable for the whole reactor lifetime. Since there is no published research about dropwise condensation for physically processed surface on SUS and Ti, the purposes of this research are to measure the condensation heat transfer coefficient and analyze its mechanism of enhanced heat transfer of treated SUS and Ti commonly used to nuclear plant. In the comparison of theoretical equation and experiment, it shows same result that heat transfer coefficient is proportional to maximum droplet diameter power to -0.321. Moreover, in the comparison of bare and processed surface, heat transfer coefficient decreases in processed surface

F/H Effluent Treatment Facility filtration upgrade alternative evaluations overview

Energy Technology Data Exchange (ETDEWEB)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-01-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater.

F/H Effluent Treatment Facility filtration upgrade alternative evaluations overview

Energy Technology Data Exchange (ETDEWEB)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-07-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater.

F/H effluent treatment facility filtration upgrade alternative evaluations overview

International Nuclear Information System (INIS)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-01-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater. (author)

Preliminary exploitation of industrial facility for flue gas treatment

International Nuclear Information System (INIS)

Chmielewski, A.G.; Zimek, Z.; Iller, E.; Tyminski, B.; Licki, J.

2001-01-01

Full text: High emission of SO 2 and NO x in the process of fossil fuel combustion creates a major world environmental problem. Poland which uses for energy production mainly pit and brown coal produces these pollutants as well. The certain amount of SO 2 and slightly less NO x pollutants is introduced into the atmosphere. 1/2 of SO 2 and 1/3 NO x pollution is contributed by heat and electricity generating boilers. The biggest sources of pollution are located in south west side of Poland and are connected with industrial centers but over 45% of the total 802 and 69% of NO x pollutants distributed over polish territory come from external sources. The laboratory facility for flue gas treatment radiation technology was organized in Institute of Nuclear Chemistry and Technology at Warsaw at the end of 80s. Soon after the pilot plant for flue gas treatment with electron beam has been installed at Power Plant Kaweczyn near Warsaw. The flow capacity trough those installations was respectively 400 and 20000 Nm /h. Three new elements have been introduced to the construction of the radiation chamber in Polish pilot installation. Those are: cascade double stage irradiation, longitudinal irradiation, (beam scanned along the chamber axis) and the air blow under the chamber window with the purpose to create air curtain separating the window from the flue gases causing corrosion. Three different system for filtration aid has been constructed and tested: bag filter, gravel bead filter and electrostatic precipitator. The pilot plant installation was used to establish the optimal parameters of industrial facility: optimizing of the process parameters leading to reduction of energy with high efficiency of SO 2 and NO x removal; selecting and testing filter devices and filtration process; developing of the monitoring and control systems at industrial plant for flue gas cleaning, preparation of the design for industrial scale facility. The positive results of the tests performed on

Exhaust gas processing facility

International Nuclear Information System (INIS)

Terada, Shin-ichi.

1995-01-01

The facility of the present invention comprises a radioactive liquid storage vessel, an exhaust gas dehumidifying device for dehumidifying gases exhausted from the vessel and an exhaust gas processing device for reducing radioactive materials in the exhaust gases. A purified gas line is disposed to the radioactive liquid storage vessel for purging exhaust gases generated from the radioactive liquid, then dehumidified and condensed liquid is recovered, and exhaust gases are discharged through an exhaust gas pipe disposed downstream of the exhaust gas processing device. With such procedures, the scale of the exhaust gas processing facility can be reduced and exhaust gases can be processed efficiently. (T.M.)

Implementation of non-condensable gases condensation suppression model into the WCOBRA/TRAC-TF2 LOCA safety evaluation code

Energy Technology Data Exchange (ETDEWEB)

Liao, J.; Cao, L.; Ohkawa, K.; Frepoli, C. [LOCA Integrated Services I, Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01

The non-condensable gases condensation suppression model is important for a realistic LOCA safety analysis code. A condensation suppression model for direct contact condensation was previously developed by Westinghouse using first principles. The model is believed to be an accurate description of the direct contact condensation process in the presence of non-condensable gases. The Westinghouse condensation suppression model is further revised by applying a more physical model. The revised condensation suppression model is thus implemented into the WCOBRA/TRAC-TF2 LOCA safety evaluation code for both 3-D module (COBRA-TF) and 1-D module (TRAC-PF1). Parametric study using the revised Westinghouse condensation suppression model is conducted. Additionally, the performance of non-condensable gases condensation suppression model is examined in the ACHILLES (ISP-25) separate effects test and LOFT L2-5 (ISP-13) integral effects test. (authors)

Development of safeguards information treatment system at facility level in Korea

International Nuclear Information System (INIS)

So, D.S.; Lee, B.D.; Song, D.Y.

2001-01-01

Safeguards Information Treatment System (SITS) at Facility level was developed to implement efficiently the obligations under IAEA comprehensive Safeguards Agreement, bilateral nuclear cooperation Agreements with other countries and domestic law, and to manage efficiently the information related to safeguards implementation at facility level in Korea. Nuclear facilities in Korea are categorized into 8 types based on its accounting characteristics as follows: (1) Item counting facility or bulk handling facility; (2) Batch follow-up facility or not; (3) MUF (Material Unaccounted For) occurrence or not; (4) Nuclear production facility or not; (5) Operation status of facility; (6) Information management of nuclear material transfer status between KMPs or not; (7) Indication of inventory KMP on the inventory change of nuclear material is required or not. Hardware and Software for SITS can be loaded on a personal computer under operation system of Window 2000 or Window NT. MS SQL server 7 and MS Internet Information Server were adopted for database management system and Web server, respectively. Network environment of SITS was designed to include nuclear research institute, nuclear power plants of PWR and CANDU, nuclear fuel fabrication facilities and other facilities. SITS can be operated standalone or under the client-server system if intranet exists. More detailed contents of SITS are described elsewhere. Each module of SITS will be tested during incorporation of existing data into SITS and SITS will be distributed to nuclear facilities in Korea

Analysis of loads and fluid-structure interactions in a condensation pool

Energy Technology Data Exchange (ETDEWEB)

Timperi, A.; Paettikangas, T.; Niemi, J. [VTT, Technical Research Centre of Finland (Finland)

2007-04-15

A simplified direct contact condensation model was implemented into the Volume of Fluid model of the Fluent CFD code. Transient three-dimensional test runs for the POOLEX experiments, where steam is blown into a water pool were performed. The model was found to provide too small condensation rate for steam when compared to experiments. In addition, the calculated back and forth oscillation of the steam water interface was much smaller than in the experiments. The model was found to be numerically quite robust. The discrepancies of the simulation, such as the too small condensation rate, could be to some extent cured by making improvements into the condensation model. As an alternative estimation method of thermohydraulic loads in condensation pools, the SILA code based on potential flow theory, was taken into use. SILA solves the pressure distribution caused by oscillating bubbles in a pool, and is easier to use and more flexible than Method of Images studied earlier. SILA has been modified for pools without an inner cylinder and test simulations for the POOLEX water pool were performed. The MpCCI FSI coupling software employs an explicit coupling scheme, which results in numerical instability in the case of the POOLEX facility. In order to improve stability, ways for implementing an implicit coupling scheme with MpCCI were examined. It was found that such a scheme is difficult to achieve without access to the source codes. An implicit coupling scheme is expected to be available with MpCCI in forthcoming years. A method was developed which can be used for analysing two-way FSI problems realistically by using only one-way coupling of CFD and structural analysis codes. In the method, the mass of the fluid is accounted for in the structural motion by adding the fluid to the structural model as an acoustic medium. Validity of the method was examined with promising results mathematically by an order of magnitude analysis and by comparing numerical results with a full

Presence of Siloxanes in the Biogas of a Wastewater Treatment Plant Separation in Condensates and Influence of the Dose of Iron Chloride on its Elimination

Energy Technology Data Exchange (ETDEWEB)

Mariano, García [Empresa Mixta de Aguas Residuales de Alicante, S.A. (EMARASA) (Spain); Daniel, Prats; Arturo, Trapote, E-mail: atj@ua.es [University Institute of Water and Environmental Sciences, University of Alicante (Spain)

2015-12-21

The siloxanes present in the biogas produced during anaerobic digestion damage the mechanism of cogeneration equipment and, consequently, negatively affect the energy valorization process. For this reason, the detection and elimination of these silicon-derived chemical compounds are a priority in the management of cogeneration facilities. In this regard, the objectives of this paper are, firstly, to characterize the siloxanes in the biogas and, secondly, to qualitatively evaluate the influence of the dose of iron chloride on its elimination. The research was performed at the Rincón de León Wastewater Treatment Plant (Alicante, Spain). The outflow biogas of the digesters and of the pressurized gasometers was sampled and analyzed. The results obtained made it possible to demonstrate, firstly, the absence of linear siloxanes and that, of the cyclic siloxanes, the predominant type was decamethylcyclopentasiloxane, and, secondly, that the addition of iron chloride in the digesters significantly reduces the siloxane content in the biogas. Additionally, it was demonstrated that the process of compression of the biogas, with the elimination of condensates, also produces significant reductions in the concentration of siloxanes in the biogas.

Presence of Siloxanes in the Biogas of a Wastewater Treatment Plant Separation in Condensates and Influence of the Dose of Iron Chloride on its Elimination

International Nuclear Information System (INIS)

Mariano, García; Daniel, Prats; Arturo, Trapote

2015-01-01

The siloxanes present in the biogas produced during anaerobic digestion damage the mechanism of cogeneration equipment and, consequently, negatively affect the energy valorization process. For this reason, the detection and elimination of these silicon-derived chemical compounds are a priority in the management of cogeneration facilities. In this regard, the objectives of this paper are, firstly, to characterize the siloxanes in the biogas and, secondly, to qualitatively evaluate the influence of the dose of iron chloride on its elimination. The research was performed at the Rincón de León Wastewater Treatment Plant (Alicante, Spain). The outflow biogas of the digesters and of the pressurized gasometers was sampled and analyzed. The results obtained made it possible to demonstrate, firstly, the absence of linear siloxanes and that, of the cyclic siloxanes, the predominant type was decamethylcyclopentasiloxane, and, secondly, that the addition of iron chloride in the digesters significantly reduces the siloxane content in the biogas. Additionally, it was demonstrated that the process of compression of the biogas, with the elimination of condensates, also produces significant reductions in the concentration of siloxanes in the biogas

Design of safeguards information treatment system at the facility level

Energy Technology Data Exchange (ETDEWEB)

Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

2001-05-01

We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system.

Design of safeguards information treatment system at the facility level

International Nuclear Information System (INIS)

Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

2001-05-01

We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system

Effect of flow velocity on the process of air-steam condensation in a vertical tube condenser

Science.gov (United States)

Havlík, Jan; Dlouhý, Tomáš

2018-06-01

This article describes the influence of flow velocity on the condensation process in a vertical tube. For the case of condensation in a vertical tube condenser, both the pure steam condensation process and the air-steam mixture condensation process were theoretically and experimentally analyzed. The influence of steam flow velocity on the value of the heat transfer coefficient during the condensation process was evaluated. For the condensation of pure steam, the influence of flow velocity on the value of the heat transfer coefficient begins to be seen at higher speeds, conversely, this effect is negligible at low values of steam velocity. On the other hand, for the air-steam mixture condensation, the influence of flow velocity must always be taken into account. The flow velocity affects the water vapor diffusion process through non-condensing air. The presence of air significantly reduces the value of the heat transfer coefficient. This drop in the heat transfer coefficient is significant at low velocities; on the contrary, the decrease is relatively small at high values of the velocity.

Status of proton treatment facility at National Cancer Center, Kashiwa

International Nuclear Information System (INIS)

Tachikawa, T.; Kohmura, I.; Kataoka, S.; Nonaka, H.; Kimura, T.; Sato, T.; Nishio, T.; Shimbo, M.; Ogino, T.; Ikeda, H.

2001-01-01

Proton treatment facility at National Cancer Center Hospital East (Kashiwa) has two rotating gantry ports and one horizontal fixed port. In order to provide the same dose distribution at different gantry angles, the beam optics from the accelerator (235 MeV cyclotron) to the entrance of nozzle is specially tuned. Recently developed automatic tuning method of beam alignment can realize a sequential treatment at three irradiation ports. (author)

Lifespan estimation of seal welded super stainless steels for water condenser of nuclear power plants

Science.gov (United States)

Kim, Young Sik; Park, Sujin; Chang, Hyun Young

2014-01-01

When sea water was used as cooling water for water condenser of nuclear power plants, commercial stainless steels can not be applied because chloride concentration exceeds 20,000 ppm. There are many opinions for the materials selection of tube and tube sheets of a condenser. This work reviewed the application guide line of stainless steels for sea-water facilities and the estimation equations of lifespan were proposed from the analyses of both field data for sea water condenser and experimental results of corrosion. Empirical equations for lifespan estimation were derived from the pit initiation time and re-tubing time of stainless steel tubing in sea water condenser of nuclear power plants. The lifespan of seal-welded super austenitic stainless steel tube/tube sheet was calculated from these equations. Critical pitting temperature of seal-welded PRE 50 grade super stainless steel was evaluated as 60 °C. Using the proposed equation in engineering aspect, tube pitting corrosion time of seal-welded tube/tube sheet was calculated as 69.8 years and re-tubing time was estimated as 82.0 years.

Malaria prevalence and treatment of febrile patients at health facilities and medicine retailers in Cameroon.

Science.gov (United States)

Mangham, Lindsay J; Cundill, Bonnie; Achonduh, Olivia A; Ambebila, Joel N; Lele, Albertine K; Metoh, Theresia N; Ndive, Sarah N; Ndong, Ignatius C; Nguela, Rachel L; Nji, Akindeh M; Orang-Ojong, Barnabas; Wiseman, Virginia; Pamen-Ngako, Joelle; Mbacham, Wilfred F

2012-03-01

To investigate the quality of malaria case management in Cameroon 5 years after the adoption of artemisinin-based combination therapy (ACT). Treatment patterns were examined in different types of facility, and the factors associated with being prescribed or receiving an ACT were investigated. A cross-sectional cluster survey was conducted among individuals of all ages who left public and private health facilities and medicine retailers in Cameroon and who reported seeking treatment for a fever. Prevalence of malaria was determined by rapid diagnostic tests (RDTs) in consenting patients attending the facilities and medicine retailers. Among the patients, 73% were prescribed or received an antimalarial, and 51% were prescribed or received an ACT. Treatment provided to patients significantly differed by type of facility: 65% of patients at public facilities, 55% of patients at private facilities and 45% of patients at medicine retailers were prescribed or received an ACT (P = 0.023). The odds of a febrile patient being prescribed or receiving an ACT were significantly higher for patients who asked for an ACT (OR = 24.1, P < 0.001), were examined by the health worker (OR = 1.88, P = 0.021), had not previously sought an antimalarial for the illness (OR = 2.29, P = 0.001) and sought treatment at a public (OR = 3.55) or private facility (OR = 1.99, P = 0.003). Malaria was confirmed in 29% of patients and 70% of patients with a negative result were prescribed or received an antimalarial. Malaria case management could be improved. Symptomatic diagnosis is inefficient because two-thirds of febrile patients do not have malaria. Government plans to extend malaria testing should promote rational use of ACT; though, the introduction of rapid diagnostic testing needs to be accompanied by updated clinical guidelines that provide clear guidance for the treatment of patients with negative test results. © 2011 Blackwell Publishing Ltd.

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1988-01-01

This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations

Environmental Protection Agency (EPA) Facility Registry Service (FRS) Wastewater Treatment Plants

Data.gov (United States)

Department of Homeland Security — This GIS dataset contains data on wastewater treatment plants, based on EPA's Facility Registry Service (FRS) and NPDES, along with Clean Watersheds Needs Survey...

Operation, Maintenance and Management of Wastewater Treatment Facilities: A Bibliography of Technical Documents.

Science.gov (United States)

Himes, Dottie

This is an annotated bibliography of wastewater treatment manuals. Fourteen manuals are abstracted including: (1) A Planned Maintenance Management System for Municipal Wastewater Treatment Plants; (2) Anaerobic Sludge Digestion, Operations Manual; (3) Emergency Planning for Municipal Wastewater Treatment Facilities; (4) Estimating Laboratory Needs…

Condensation: the new deal; Condensation: la nouvelle donne

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

The principle of condensation boilers is based on the recovery of the latent heat of the steam generated by the combustion of natural gas. This technology was introduced in France at the end of the 80's but failed in its promise because of the complexity of the equipments available at that time. Today, constructors' offer is more mature and reliable and the context has changed. This technology can conciliate three goals: a mastery of energy consumptions, the comfort of the user and the respect of environment. This meeting organized by the research center of Gaz de France (Cegibat), was a good opportunity to makes a status of the market of individual condensation systems in France and in Europe, to present the situation of this technology today and the 10 golden rules for the fitting and maintenance of individual condensation boilers, and to present some technical references, examples and results of today's offer. (J.S.)

The TOPFLOW multi-purpose thermohydraulic test facility

International Nuclear Information System (INIS)

Schaffrath, Andreas; Kruessenberg, A.-K.; Weiss, F.-P.; Prasser, H.-M.

2002-01-01

The TOPFLOW (Transient Two Phase Flow Test Facility) multi-purpose thermohydraulic test facility is being built for studies of steady-state and transient flow phenomena in two-phase flows, and for the development and validation of the models contained in CFD (Computational Fluid Dynamics) codes. The facility is under construction at the Institute for Safety Research of the Rossendorf Research Center (FZR). It will be operated together with the Dresden Technical University and the Zittau/Goerlitz School for Technology, Economics and Social Studies within the framework of the Nuclear Technology Competence Preservation Program. TOPFLOW, with its test sections and its flexible concept, is available as an attractive facility also to users from all European countries. Experiments are planned in these fields, among others: - Transient two-phase flows in vertical and horizontal pipes and pipes of any inclination as well as in geometries typical of nuclear reactors (annulus, hot leg). - Boiling in large vessels and water pools (measurements of steam generation, 3D steam content distribution, turbulence, temperature stratification). - Test of passive components and safety systems. - Condensation in horizontal pipes in the absence and presence of non-condensable gases. The construction phase of TOPFLOW has been completed more or less on schedule. Experiments can be started after a commissioning phase in the 3rd quarter of 2002. (orig.) [de

Risk management program for the 283-W water treatment facility

International Nuclear Information System (INIS)

Green, W.E.

1999-01-01

This Risk Management (RM) Program covers the 283-W Water Treatment Facility (283W Facility), located in the 200 West Area of the Hanford Site. A RM Program is necessary for this facility because it stores chlorine, a listed substance, in excess of or has the potential to exceed the threshold quantities defined in Title 40 of the Code of Federal Regulations (CFR) Part 68 (EPA, 1998). The RM Program contains data that will be used to prepare a RM Plan, which is required by 40 CFR 68. The RM Plan is a summary of the RM Program information, contained within this document, and will be submitted to the U.S. Environmental Protection Agency (EPA) ultimately for distribution to the public. The RM Plan will be prepared and submitted separately from this document

A porous media calculation for the isolation condenser heat transfer and circulation

International Nuclear Information System (INIS)

Jaakko, Miettinen; Ismo, Karppinen

2003-01-01

In the development of advanced light water reactors, thermohydraulic phenomena are versatile in comparison with the present concepts. The new features include, for example, passive safety systems, where energy transport takes place by natural circulation instead of forced flow. In the isolation condenser, the steam generated in the reactor vessel is conduced into the heat transfer tubes. The tube bundle has been submerged into a large water pool, where the heat flux through the tube wall initially is heating the subcooled water, but rather soon boiling take place. The temperature differences and void fraction in the pool create large two-phase circulation. For modeling of the entire condenser a combined application of two types of simulation models has been selected. For the whole geometry, a porous media solution has been developed, where the existence of the heat transfer tubes in the water pool and their heat generation is described by the porous media approach. The 3-dimensional solution of two-phase equations is based on the drift-flux formalism. The condensation and liquid film generation inside the heat transfer tube is modelled using a 1-dimensional model considering the steam core, liquid film and heat transfer tube. The heat flux through the tube wall defines the boundary conditions for the water pool. Parallel to the porous media development for the entire process facility, the phase change models have been improved for Fluent 6 mixture model, and the code is used for analysing in detail the heat transfer around the tubing. The purpose in the analyses is to obtain more detailed information of the flow field and vapour distribution around the tube bundle. By combining the porous media model for the entire facility, with the CFD models for the two-phase flow details around the heat transfer tubes and experimental studies the most important mechanisms around the condensation pool can be gathered. In this context the porous media model is considered. (author)

Hazardous air pollutant (HAP) emission characterization of sewage treatment facilities in Korea.

Science.gov (United States)

Kang, Kyoung-Hee; Dong, Jong-In

2010-04-01

Until recently, nearly all sewage treatment-related regulations and researches have focused on the removal of the conventional and toxic pollutants from liquid effluents. The discharge of toxic compounds to the atmosphere has been implicitly regarded as a way of removal or destruction. During sewage treatment, the fate mechanism of volatilization/stripping, sorption and biotransformation primarily determines the fate of volatile HAPs. The objectives of this study are to investigate the emission characteristics of HAPs, which are generated from the liquid surface of sewage treatment facilities, by using an emission isolation flux chamber. HAP emissions increased at the inlet of the aerobic chamber during summer due to the relatively high atmospheric temperature. The percent ratio of flux for toluene reached its peak in winter, accounting for 33.6-34.2% of the total, but decreased to 25.1-28.6% in summer. In autumn, trichloroethene (TCE) was the highest, recording 17.6-18.1%, with chloroform and toluene showing similar levels. It seems that the ratio of chlorinated hydrocarbons increases in both summer and autumn because the chamber temperature during that time is higher than winter. This study is the initial study to investigate the emission characteristics of volatile HAPs emitted from domestic sewage treatment facilities to the air in Korea. Therefore, the isolation flux chamber will be used as an emission estimations tool to measure HAPs from sewage treatment facilities and may be applied to develop the emission factor and national source inventory of HAPs.

Born-Kothari Condensation for Fermions

Directory of Open Access Journals (Sweden)

Arnab Ghosh

2017-09-01

Full Text Available In the spirit of Bose–Einstein condensation, we present a detailed account of the statistical description of the condensation phenomena for a Fermi–Dirac gas following the works of Born and Kothari. For bosons, while the condensed phase below a certain critical temperature, permits macroscopic occupation at the lowest energy single particle state, for fermions, due to Pauli exclusion principle, the condensed phase occurs only in the form of a single occupancy dense modes at the highest energy state. In spite of these rudimentary differences, our recent findings [Ghosh and Ray, 2017] identify the foregoing phenomenon as condensation-like coherence among fermions in an analogous way to Bose–Einstein condensate which is collectively described by a coherent matter wave. To reach the above conclusion, we employ the close relationship between the statistical methods of bosonic and fermionic fields pioneered by Cahill and Glauber. In addition to our previous results, we described in this mini-review that the highest momentum (energy for individual fermions, prerequisite for the condensation process, can be specified in terms of the natural length and energy scales of the problem. The existence of such condensed phases, which are of obvious significance in the context of elementary particles, have also been scrutinized.

Condensation in Nanoporous Packed Beds.

Science.gov (United States)

Ally, Javed; Molla, Shahnawaz; Mostowfi, Farshid

2016-05-10

In materials with tiny, nanometer-scale pores, liquid condensation is shifted from the bulk saturation pressure observed at larger scales. This effect is called capillary condensation and can block pores, which has major consequences in hydrocarbon production, as well as in fuel cells, catalysis, and powder adhesion. In this study, high pressure nanofluidic condensation studies are performed using propane and carbon dioxide in a colloidal crystal packed bed. Direct visualization allows the extent of condensation to be observed, as well as inference of the pore geometry from Bragg diffraction. We show experimentally that capillary condensation depends on pore geometry and wettability because these factors determine the shape of the menisci that coalesce when pore filling occurs, contrary to the typical assumption that all pore structures can be modeled as cylindrical and perfectly wetting. We also observe capillary condensation at higher pressures than has been done previously, which is important because many applications involving this phenomenon occur well above atmospheric pressure, and there is little, if any, experimental validation of capillary condensation at such pressures, particularly with direct visualization.

Comparison of Heat Transfer Coefficients of Silver Coated and Chromium Coated Copper Tubes of Condenser in Dropwise Condensation

OpenAIRE

Er. Shivesh Kumar; Dr. Amit Kumar

2016-01-01

Since centuries steam is being used in power generating system. The steam leaving the power unit is reconverted into water in a condenser designed to transfer heat from the steam to the cooling water as rapidly and as efficiently as possible. The efficiency of condenser depends on rate of condensation and mode of condensation of steam in the condenser. The increase in efficiency of the condenser enhances the heat transfer co-efficient which in turn results in economic design of condenser and ...

Bio-oil fractionation and condensation

Science.gov (United States)

Brown, Robert C; Jones, Samuel T; Pollard, Anthony

2013-07-02

A method of fractionating bio-oil vapors which involves providing bio-oil vapors comprising bio-oil constituents is described. The bio-oil vapors are cooled in a first stage which comprises a condenser having passages for the bio-oil separated by a heat conducting wall from passages for a coolant. The coolant in the condenser of the first stage is maintained at a substantially constant temperature, set at a temperature in the range of 75 to 100.degree. C., to condense a first liquid fraction of liquefied bio-oil constituents in the condenser of the first stage. The first liquid fraction of liquified bio-oil constituents from the condenser in the first stage is collected. Also described are steps for subsequently recovering further liquid fractions of liquefied bio-oil constituents. Particular compositions of bio-oil condensation products are also described.

Condenser performance monitoring and cleaning

International Nuclear Information System (INIS)

Walden, J.V.

1998-01-01

The main condenser at Ginna Station was retubed from admiralty brass to 316 stainless steel. A condenser performance monitoring spreadsheet was developed using EPRI guidelines after fouling was discovered. PEPSE computer models were used to determine the power loss and confirm the spreadsheet results. Cleaning of the condenser was performed using plastic scrubbers. Condenser performance improved dramatically following the cleaning. PEPSE, condenser spreadsheet performance, and actual observed plant data correlated well together. The fouling mechanism was determined to be a common lake bacteria and fungus growth which was combined with silt. Chlorination of the circulating water system at the allowable limits is keeping the biofouling under control

Modelling the thermodynamic performance of a concentrated solar power plant with a novel modular air-cooled condenser

International Nuclear Information System (INIS)

Moore, J.; Grimes, R.; Walsh, E.; O'Donovan, A.

2014-01-01

This paper aims at developing a novel air-cooled condenser for concentrated solar power plants. The condenser offers two significant advantages over the existing state-of-the-art. Firstly, it can be installed in a modular format where pre-assembled condenser modules reduce installation costs. Secondly, instead of using large fixed speed fans, smaller speed controlled fans are incorporated into the individual modules. This facility allows the operating point of the condenser to change and continuously maximise plant efficiency. A thorough experimental analysis was performed on a number of prototype condenser designs. This analysis investigated the validly and accuracy of correlations from literature in predicting the thermal and aerodynamic characteristics of different designs. These measurements were used to develop a thermodynamic model to predict the performance of a 50 MW CSP (Concentrated Solar Power) plant with various condenser designs installed. In order to compare different designs with respect to the specific plant capital cost, a techno-economic analysis was performed which identified the optimum size of each condenser. The results show that a single row plate finned tube design, a four row, and a two row circular finned tube design are all similar in terms of their techno-economic performance and offer significant savings over other designs. - Highlights: • A novel air cooled condenser for CSP (Concentrated Solar Power) applications is proposed. • A thorough experimental analysis of various condenser designs was performed. • Heat transfer and flow friction correlations validated for fan generated air flow. • A thermodynamic model to calculate CSP plant output is presented. • Results show the proposed condenser design can continually optimise plant output

Chromosome condensation and segmentation

International Nuclear Information System (INIS)

Viegas-Pequignot, E.M.

1981-01-01

Some aspects of chromosome condensation in mammalians -humans especially- were studied by means of cytogenetic techniques of chromosome banding. Two further approaches were adopted: a study of normal condensation as early as prophase, and an analysis of chromosome segmentation induced by physical (temperature and γ-rays) or chemical agents (base analogues, antibiotics, ...) in order to show out the factors liable to affect condensation. Here 'segmentation' means an abnormal chromosome condensation appearing systematically and being reproducible. The study of normal condensation was made possible by the development of a technique based on cell synchronization by thymidine and giving prophasic and prometaphasic cells. Besides, the possibility of inducing R-banding segmentations on these cells by BrdU (5-bromodeoxyuridine) allowed a much finer analysis of karyotypes. Another technique was developed using 5-ACR (5-azacytidine), it allowed to induce a segmentation similar to the one obtained using BrdU and identify heterochromatic areas rich in G-C bases pairs [fr

Characteristic aspects of pion-condensed phases

International Nuclear Information System (INIS)

Takatsuka, Tatsuyuki; Tamagaki, Ryozo; Tatsumi, Toshitaka.

1993-01-01

Characteristic aspects of pion-condensed phases are described in a simple model, for the system involving only nucleons and pions which interact through the π-N P-wave interaction. We consider one typical version in each of three kinds of pion condensation; the one of neutral pions (π 0 ), the one of charged pions (π C ) and the combined one in which both the π 0 and π C condensations are coexistent. Emphasis is put on the description to clarify the novel structures of the nucleon system which are realized in the pion-condensed phases. At first, it is shown that the π 0 condensation is equivalent to the particular nucleonic phase realized by a structure change of the nucleon system, where the attractive first-order effect of the one-pion-exchange (OPE) tensor force is brought about coherently. The aspects of this phase are characterized by the layered structure with a specific spin-isospin order with one-dimensional localization (named the ALS structure in short), which provides the source function for the condensed π 0 field. We utilize both descriptions with use of fields and potentials for the π 0 condensation. Next, the π C condensation realized in neutron-rich matter is described by adopting a version of the traveling condensed wave. In this phase, the nucleonic structure becomes the Fermi gas consisting of quasi-neutrons described by a superposition of neutron and proton. In this sense the structure change of the nucleon system for the π C condensation is moderate, and the field description is suitable. Finally, we describe a coexistent pion condensation, in which both the π 0 and π C condensations coexist without interference in such a manner that the π C condensation develops in the ALS structure. The model adopted here provides us with the characteristic aspects of the pion-condensed phases persisting in the realistic situation, where other ingredients affecting the pion condensation are taken into account. (author)

Systematic text condensation

DEFF Research Database (Denmark)

Malterud, Kirsti

2012-01-01

To present background, principles, and procedures for a strategy for qualitative analysis called systematic text condensation and discuss this approach compared with related strategies.......To present background, principles, and procedures for a strategy for qualitative analysis called systematic text condensation and discuss this approach compared with related strategies....

NPDES Permit for Soap Creek Associates Wastewater Treatment Facility in Montana

Science.gov (United States)

Under National Pollutant Discharge Elimination System permit number MT-0023183, Soap Creek Associates, Inc. is authorized to discharge from its wastewater treatment facility located in West, Bighorn County, Montana, to Soap Creek.

One-Pot Synthesis of N-(α-Peroxy)Indole/Carbazole via Chemoselective Three-Component Condensation Reaction in Open Atmosphere

KAUST Repository

Wang, Xinbo; Pan, Yupeng; Huang, Kuo-Wei; Lai, Zhiping

2015-01-01

A facile one-pot synthesis of N-(α-peroxy)indole and N-(α-peroxy)carbazole has been developed using metal-free, organo-acid-catalyzed three-component condensation reactions of indole/carbazole, aldehyde, and peroxide. Based on the reaction

Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

Directory of Open Access Journals (Sweden)

Pavan K. Sharma

2012-01-01

Full Text Available In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA or beyond design basis accidents (BDBA. For accurate calculation of the temperature/pressure rise and hydrogen transport calculation in nuclear reactor containment due to such scenarios, wall condensation heat transfer coefficient (HTC is used. In the present work, the adaptation of a commercial CFD code with the implementation of models for steam condensation on wall surfaces in presence of noncondensable gases is explained. Steam condensation has been modeled using the empirical average HTC, which was originally developed to be used for “lumped-parameter” (volume-averaged modeling of steam condensation in the presence of noncondensable gases. The present paper suggests a generalized HTC based on curve fitting of most of the reported semiempirical condensation models, which are valid for specific wall conditions. The present methodology has been validated against limited reported experimental data from the COPAIN experimental facility. This is the first step towards the CFD-based generalized analysis procedure for condensation modeling applicable for containment wall surfaces that is being evolved further for specific wall surfaces within the multicompartment containment atmosphere.

The coupling of condensed matter excitations to electron probes

International Nuclear Information System (INIS)

Ritchie, R.H.

1988-01-01

Aspects of coupling of a classical electron with bulk and surface excitations in condensed matter have been sketched. Some considerations of a self-energy approach to the complete quantal treatment of this coupling have been given. 19 refs., 3 figs

Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

International Nuclear Information System (INIS)

1997-07-01

This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

Mixed and low-level waste treatment facility project

International Nuclear Information System (INIS)

1992-04-01

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies

Mixed and low-level waste treatment facility project

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

Steam generators, turbines, and condensers. Volume six

International Nuclear Information System (INIS)

Anon.

1986-01-01

Volume six covers steam generators (How steam is generated, steam generation in a PWR, vertical U-tube steam generators, once-through steam generators, how much steam do steam generators make?), turbines (basic turbine principles, impulse turbines, reaction turbines, turbine stages, turbine arrangements, turbine steam flow, steam admission to turbines, turbine seals and supports, turbine oil system, generators), and condensers (need for condensers, basic condenser principles, condenser arrangements, heat transfer in condensers, air removal from condensers, circulating water system, heat loss to the circulating water system, factors affecting condenser performance, condenser auxiliaries)

Economic impacts of zebra mussels on drinking water treatment and electric power generation facilities.

Science.gov (United States)

Connelly, Nancy A; O'Neill, Charles R; Knuth, Barbara A; Brown, Tommy L

2007-07-01

Invasions of nonnative species such as zebra mussels can have both ecological and economic consequences. The economic impacts of zebra mussels have not been examined in detail since the mid-1990s. The purpose of this study was to quantify the annual and cumulative economic impact of zebra mussels on surface water-dependent drinking water treatment and electric power generation facilities (where previous research indicated the greatest impacts). The study time frame was from the first full year after discovery in North America (Lake St. Clair, 1989) to the present (2004); the study area was throughout the mussels' North American range. A mail survey resulted in a response rate of 31% for electric power companies and 41% for drinking water treatment plants. Telephone interviews with a sample of nonrespondents assessed nonresponse bias; only one difference was found and adjusted for. Over one-third (37%) of surveyed facilities reported finding zebra mussels in the facility and almost half (45%) have initiated preventive measures to prevent zebra mussels from entering the facility operations. Almost all surveyed facilities (91%) with zebra mussels have used control or mitigation alternatives to remove or control zebra mussels. We estimated that 36% of surveyed facilities experienced an economic impact. Expanding the sample to the population of the study area, we estimated 267 million dollars (BCa 95% CI = 161 million dollars - 467 million dollars) in total economic costs for electric generation and water treatment facilities through late 2004, since 1989. Annual costs were greater (44,000 dollars/facility) during the early years of zebra mussel infestation than in recent years (30,000 dollars). As a result of this and other factors, early predictions of the ultimate costs of the zebra mussel invasion may have been excessive.

Development of safeguards information treatment system at the facility level

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Doo; Song, Dae Yong; So, Dong Sup; Kwack, Eun Ho [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-04-01

Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described. 3 tabs. (Author)

A CFD study of wave influence on film steam condensation in the presence of non-condensable gas

Energy Technology Data Exchange (ETDEWEB)

Wang, Xianmao, E-mail: xm-wang11@mails.tsinghua.edu.cn [Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Chang, Huajian, E-mail: changhj@tsinghua.edu.cn [Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Corradini, Michael, E-mail: corradini@engr.wisc.edu [Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)

2016-08-15

Highlights: • A condensation model is incorporated in the ANSYS FLUENT. • Different turbulence models are evaluated for flows over wavy surfaces. • Wavy surfaces with and without moving velocities are used to model the wave. • Various wavy surfaces with different wave heights and wavelengths are selected. • Wave influence on film steam condensation is investigated. - Abstract: Steam condensation plays an important role in removing heat from the containment of a nuclear plant during postulated accidents. However, due to the presence of non-condensable gases such as air and hydrogen in the containment, the condensation rate can decrease dramatically. Under certain conditions, the condensate film on the cold containment walls can affect the overall heat transfer rate. The wavy interface of the condensate film is a factor and is usually believed to enhance the condensation rate, since the waves can both increase the interfacial area and disturb the non-condensable gas boundary layer. However, it is not clear how to properly account for this factor and what is its quantitative influence in experiments. In this work, a CFD approach is applied to study the wave effects on film condensation in the presence of non-condensable gas. Wavy surfaces with and without moving velocities are used to replace the wavy interface of the falling film. A condensation model is incorporated in the ANSYS FLUENT simulation and a realizable k–ε turbulence model is applied. Various wavy surfaces with different wave heights and wavelengths are selected to conduct numerical experiments with a wide range of gas velocities. The results show that the wave structure can enhance condensation rate up to ten percent mainly due to the alteration of local flow structures in the gas phase. The increments of the condensation rate due to the wavy interface can vary with different gas velocities. The investigation shows that a multiplication factor accounts for the wave effects on film

Effect of condenser water in-leakage on steam generator water chemistry

International Nuclear Information System (INIS)

Balakrishnan, P.V.

1978-01-01

Corrosive environments may be generated within steam genrators from condenser cooling water in-leakage. Theoretical as well as experimental evaluation of the aggressiveness of such environments is being carried out for the condenser-cooling waters used at CANDU-PHW nuclear power stations. Calculations have shown that highly concentrated chloride solutions - acidic in the case of sea-water in-leakage, and alkaline in the rest of the cases considered - would be produced within the steam generator. Experiments in a model boiler showed that sea-water in-leakage caused rapid corrosion of carbon steel components when only AVT (all volatile treatment) was used for water chemistry control. Use of a non-volatile reagent, as in the congruent phosphate treatment, avoided the rapid corrosion of carbon steel. On the basis of our studies, congruent phosphate treatment during sea water in-leakage appears desirable. (author)

Geographic access to radiation therapy facilities and disparities of early-stage breast cancer treatment

Directory of Open Access Journals (Sweden)

Yan Lin

2018-05-01

Full Text Available Few studies of breast cancer treatment have focused on the Northern Plains of the United States, an area with a high mastectomy rate. This study examined the association between geographic access to radiation therapy facilities and receipt of breast cancer treatments among early-stage breast cancer patients in South Dakota. Based on 4,209 early-stage breast cancer patients diagnosed between 2001 and 2012 in South Dakota, the study measured geographic proximity to radiation therapy facilities using the shortest travel time for patients to the closest radiation therapy facility. Two-level logistic regression models were used to estimate for early stage cases i the odds of mastectomy versus breast conserving surgery (BCS; ii the odds of not receiving radiation therapy after BCS versus receiving follow-up radiation therapy. Covariates included race/ethnicity, age at diagnosis, tumour grade, tumour sequence, year of diagnosis, census tract-level poverty rate and urban/rural residence. The spatial scan statistic method was used to identify geographic areas with significantly higher likelihood of experiencing mastectomy. The study found that geographic accessibility to radiation therapy facilities was negatively associated with the likelihood of receiving mastectomy after adjustment for other covariates, but not associated with radiation therapy use among patients receiving BCS. Compared with patients travelling less than 30 minutes to a radiation therapy facility, patients travelling more than 90 minutes were about 1.5 times more likely to receive mastectomy (odds ratio, 1.51; 95% confidence interval, 1.08-2.11 and patients travelling more than 120 minutes were 1.7 times more likely to receive mastectomy (odds ratio, 1.70; 95% confidence interval, 1.19-2.42. The study also identified a statistically significant cluster of patients receiving mastectomy who were located in south-eastern South Dakota, after adjustment for other factors. Because

Functional implications of plasma membrane condensation for T cell activation.

Directory of Open Access Journals (Sweden)

Carles Rentero

2008-05-01

Full Text Available The T lymphocyte plasma membrane condenses at the site of activation but the functional significance of this receptor-mediated membrane reorganization is not yet known. Here we demonstrate that membrane condensation at the T cell activation sites can be inhibited by incorporation of the oxysterol 7-ketocholesterol (7KC, which is known to prevent the formation of raft-like liquid-ordered domains in model membranes. We enriched T cells with 7KC, or cholesterol as control, to assess the importance of membrane condensation for T cell activation. Upon 7KC treatment, T cell antigen receptor (TCR triggered calcium fluxes and early tyrosine phosphorylation events appear unaltered. However, signaling complexes form less efficiently on the cell surface, fewer phosphorylated signaling proteins are retained in the plasma membrane and actin restructuring at activation sites is impaired in 7KC-enriched cells resulting in compromised downstream activation responses. Our data emphasizes lipids as an important medium for the organization at T cell activation sites and strongly indicates that membrane condensation is an important element of the T cell activation process.

Latest development in project site radwaste treatment facility (SRTF) Sanmen

International Nuclear Information System (INIS)

Mennicken, K.; Lohmann, P.

2015-01-01

Westinghouse Electric Germany GmbH (WEG) was successful in being awarded a contract as to the planning, delivery, installation and commissioning of radwaste treatment systems for the AP1000 units at Sanmen site, PR China. Operational low and intermediate level radioactive waste will be processed in the Site Radwaste Treatment Facility (SRTF). This paper explains the latest developments of the project, especially the experience with customer-hired Chinese planning partners, installation companies and Customer operating personnel. (authors)

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1988-01-01

This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 appendices covering engineering drawings and operating procedures

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1988-01-01

This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constitutents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 Appendices covering engineering drawings and operating procedures

Grout Treatment Facility dangerous waste permit application

International Nuclear Information System (INIS)

1988-01-01

This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 14 Appendices. Topics include Engineering Drawings, Maps, Roads, Toxicity Testing, and Pilot-Scale Testing

Accident localization system with jet condensers for VVER 440-V 230 NPP at Jaslovske Bohunice

International Nuclear Information System (INIS)

Murani, J.

1995-01-01

The operational safety of the V1 nuclear power plant (NPP) is unsatisfactory and does not correspond to present requirements as to nuclear safety. Further NPP operation after 1995 is conditional on nuclear safety enhancement to a level comparable with that in West European countries. This aim should be achieved by a principal reconstruction involving in addition to others also backfitting the V1 NPP with technical facilities aimed at coping with a design basis accident (DBA).To cope with such an accident the Power Equipment Research Institute (VUEZ) designed an accident localization system with jet condensers. This system consists of (a) an air trap (one for each unit, mutually interconnected) with an expansion bell enclosed within, placed on a plate with 200 pipes of jet condensers passing through, and (b) a connecting duct between the hermetic zone and the air trap. The vertical jet condenser is an essential element of the system designed for steam condensation. Apart from condensation it serves as a water seal separating units 1 and 2.Demonstration tests of the jet condenser (model 1:1) condensing function were carried out at the testing unit of the All-Union Research Institute for NPP Operation (VNIIAES), Moscow in Kashir, 11-22 September 1992. These experiments proved the jet condenser ability to ensure complete condensation of the steam produced. Experimental verification of the sealing function (model 1:1) was carried out at the testing unit of the VUEZ Tlmace. These experiments concerning the dynamics and overpressure in the free space above the pool were close to the conditions in the air trap during DBA. The jet condenser height was proved to be sufficient to ensure the sealing function. Design and experimental work has been implemented in close cooperation with Russian experts Mr. V.N. Bulynin from the VNIIAES, Moscow, and Mr. M.V. Kuznecov from the Scientific and Engineering Center for Nuclear and Radiological Safety, Moscow. (orig.)

Impact assessment of the forest fires on Oarai Research and Development Center Waste Treatment Facility

International Nuclear Information System (INIS)

Shimomura, Yusuke; Kitamura, Ryoichi; Hanari, Akira; Sato, Isamu

2016-03-01

In response to new standards for regulating waste treatment facility ('new regulatory standards'; December 18, 2013 enforcement), it was carried out impact assessment of forest fires on the Waste Treatment Facility existed in Oarai Research and Development Center of Japan Atomic Energy Agency. At first, a fire spread scenario of forest fires was assumed. The intensity of forest fires was evaluated from field surveys, forest fire evaluation models and so on. As models of forest fire intensity evaluation, Rothermel Model and Canadian Forest Fire Behavior Prediction (FBP) System were used. Impact assessment of radiant heat to the facility was carried out, and temperature change of outer walls for the assumed forest fires was estimated. The outer wall temperature of facility was estimated around 160degC at the maximum, it was revealed that it doesn't reach allowable temperature limit. Consequently, it doesn't influence the strength of concrete. In addition, a probability of fire breach was estimated to be about 20%. This report illustrates an example of evaluation of forest fires for the new regulatory standards through impact assessment of the forest fires on the Waste Treatment Facility. (author)

Assessment of horizontal in-tube condensation models using MARS code. Part I: Stratified flow condensation

Energy Technology Data Exchange (ETDEWEB)

Jeon, Seong-Su [Department of Engineering Project, FNC Technology Co., Ltd., Bldg. 135-308, Seoul National University, Gwanak-gu, Seoul 151-744 (Korea, Republic of); Department of Nuclear Engineering, Seoul National University, Gwanak-gu, Seoul 151-744 (Korea, Republic of); Hong, Soon-Joon, E-mail: sjhong90@fnctech.com [Department of Engineering Project, FNC Technology Co., Ltd., Bldg. 135-308, Seoul National University, Gwanak-gu, Seoul 151-744 (Korea, Republic of); Park, Ju-Yeop; Seul, Kwang-Won [Korea Institute of Nuclear Safety, 19 Kuseong-dong, Yuseong-gu, Daejon (Korea, Republic of); Park, Goon-Cherl [Department of Nuclear Engineering, Seoul National University, Gwanak-gu, Seoul 151-744 (Korea, Republic of)

2013-01-15

Highlights: Black-Right-Pointing-Pointer This study collected 11 horizontal in-tube condensation models for stratified flow. Black-Right-Pointing-Pointer This study assessed the predictive capability of the models for steam condensation. Black-Right-Pointing-Pointer Purdue-PCCS experiments were simulated using MARS code incorporated with models. Black-Right-Pointing-Pointer Cavallini et al. (2006) model predicts well the data for stratified flow condition. Black-Right-Pointing-Pointer Results of this study can be used to improve condensation model in RELAP5 or MARS. - Abstract: The accurate prediction of the horizontal in-tube condensation heat transfer is a primary concern in the optimum design and safety analysis of horizontal heat exchangers of passive safety systems such as the passive containment cooling system (PCCS), the emergency condenser system (ECS) and the passive auxiliary feed-water system (PAFS). It is essential to analyze and assess the predictive capability of the previous horizontal in-tube condensation models for each flow regime using various experimental data. This study assessed totally 11 condensation models for the stratified flow, one of the main flow regime encountered in the horizontal condenser, with the heat transfer data from the Purdue-PCCS experiment using the multi-dimensional analysis of reactor safety (MARS) code. From the assessments, it was found that the models by Akers and Rosson, Chato, Tandon et al., Sweeney and Chato, and Cavallini et al. (2002) under-predicted the data in the main condensation heat transfer region, on the contrary to this, the models by Rosson and Meyers, Jaster and Kosky, Fujii, Dobson and Chato, and Thome et al. similarly- or over-predicted the data, and especially, Cavallini et al. (2006) model shows good predictive capability for all test conditions. The results of this study can be used importantly to improve the condensation models in thermal hydraulic code, such as RELAP5 or MARS code.

Listed waste history at Hanford facility TSD units

International Nuclear Information System (INIS)

Miskho, A.G.

1996-01-01

This document was prepared to close out an occurrence report that Westinghouse Hanford Company issued on December 29, 1994. Occurrence Report RL-WHC-GENERAL-1994-0020 was issued because knowledge became available that could have impacted start up of a Hanford Site facility. The knowledge pertained to how certain wastes on the Hanford Site were treated, stored, or disposed of. This document consolidates the research performed by Westinghouse Hanford Company regarding listed waste management at onsite laboratories that transfer waste to the Double-Shell Tank System. Liquid and solid (non-liquid) dangerous wastes and mixed wastes at the Hanford Site are generated from various Site operations. These wastes may be sampled and characterized at onsite laboratories to meet waste management requirements. In some cases, the wastes that are generated in the field or in the laboratory from the analysis of samples require further management on the Hanford Site and are aggregated together in centralized tank storage facilities. The process knowledge presented herein documents the basis for designation and management of 242-A Evaporator Process Condensate, a waste stream derived from the treatment of the centralized tank storage facility waste (the Double-Shell Tank System). This document will not be updated as clean up of the Hanford Site progresses

The NOKO/TOPFLOW facility for natural convection flow

International Nuclear Information System (INIS)

Hicken, E.F.; Jaegers, H.; Schaffrath, A.; Weiss, F.-P.

2002-01-01

For the study of the effectiveness of passive safety systems a high pressure (up to 7 MPa) and high power (up to 4 MW) test facility - named NOKO - has been constructed and operated at the Forschungszentrum Juelich. From 1996-1998 this facility was used for a project within the 4th FP of the EU 'European BWR R and D Cluster for Innovative Passive Safety Systems'. An overview and selected results are given for the tests with two bundles of the emergency condenser, with the building and plate condenser, with 4 different passive initiators, with a passive flooding system and with decay heat removal tests during shutdown. It has been decided to decrease substantially the safety research at the Forschungszentrum Juelich; to maintain the experimental competence for two-phase flow the NOKO facility will be transferred to the Forschungszentrum Rossendorf by the end of the year 2000 up to the beginning of the year 2001. The facility will be named TOPFLOW; the main objectives of future tests will be oriented towards more generic research: investigation of steady state and transient two-phase flow phenomena especially transient two-phase flow patterns, the development of two-phase flow instrumentation, the generation of a data basis for Computational Fluid Dynamic (CFD)-Code validation and testing of heat exchangers and safety systems. An overview will be given about the modifications and improvements related to the test facility and the planned tests. (author)

Opportunities for Energy Efficiency and Open Automated Demand Response in Wastewater Treatment Facilities in California -- Phase I Report

Energy Technology Data Exchange (ETDEWEB)

Lekov, Alex; Thompson, Lisa; McKane, Aimee; Song, Katherine; Piette, Mary Ann

2009-04-01

This report summarizes the Lawrence Berkeley National Laboratory?s research to date in characterizing energy efficiency and automated demand response opportunities for wastewater treatment facilities in California. The report describes the characteristics of wastewater treatment facilities, the nature of the wastewater stream, energy use and demand, as well as details of the wastewater treatment process. It also discusses control systems and energy efficiency and automated demand response opportunities. In addition, several energy efficiency and load management case studies are provided for wastewater treatment facilities.This study shows that wastewater treatment facilities can be excellent candidates for open automated demand response and that facilities which have implemented energy efficiency measures and have centralized control systems are well-suited to shift or shed electrical loads in response to financial incentives, utility bill savings, and/or opportunities to enhance reliability of service. Control technologies installed for energy efficiency and load management purposes can often be adapted for automated demand response at little additional cost. These improved controls may prepare facilities to be more receptive to open automated demand response due to both increased confidence in the opportunities for controlling energy cost/use and access to the real-time data.

Development of an Integrated Leachate Treatment Solution for the Port Granby Waste Management Facility - 12429

Energy Technology Data Exchange (ETDEWEB)

Conroy, Kevin W. [Golder Associates Inc., Lakewood, Colorado (United States); Vandergaast, Gerald [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada)

2012-07-01

The Port Granby Project (the Project) is located near the north shore of Lake Ontario in the Municipality of Clarington, Ontario, Canada. The Project consists of relocating approximately 450,000 m{sup 3} of historic Low-Level Radioactive Waste (LLRW) and contaminated soil from the existing Port Granby Waste Management Facility (WMF) to a proposed Long-Term Waste Management Facility (LTWMF) located adjacent to the WMF. The LTWMF will include an engineered waste containment facility, a Wastewater Treatment Plant (WTP), and other ancillary facilities. A series of bench- and pilot-scale test programs have been conducted to identify preferred treatment processes to be incorporated into the WTP to treat wastewater generated during the construction, closure and post-closure periods at the WMF/LTWMF. (authors)

Do drug treatment facilities increase clients' exposure to potential neighborhood-level triggers for relapse? A small-area assessment of a large, public treatment system.

Science.gov (United States)

Jacobson, Jerry O

2006-03-01

Research on drug treatment facility locations has focused narrowly on the issue of geographic proximity to clients. We argue that neighborhood conditions should also enter into the facility location decision and illustrate a formal assessment of neighborhood conditions at facilities in a large, metropolitan area, taking into account conditions clients already face at home. We discuss choice and construction of small-area measures relevant to the drug treatment context, including drug activity, disadvantage, and violence as well as statistical comparisons of clients' home and treatment locations with respect to these measures. Analysis of 22,707 clients discharged from 494 community-based outpatient and residential treatment facilities that received public funds during 1998-2000 in Los Angeles County revealed no significant mean differences between home and treatment neighborhoods. However, up to 20% of clients are exposed to markedly higher levels of disadvantage, violence, or drug activity where they attend treatment than where they live, suggesting that it is not uncommon for treatment locations to increase clients' exposure to potential environmental triggers for relapse. Whereas on average both home and treatment locations exhibit higher levels of these measures than the household locations of the general population, substantial variability in public treatment clients' home neighborhoods calls into question the notion that they hail exclusively from poor, high drug activity areas. Shortcomings of measures available for neighborhood assessment of treatment locations and implications of the findings for other areas of treatment research are also discussed.

Off gas condenser performance modelling

International Nuclear Information System (INIS)

Cains, P.W.; Hills, K.M.; Waring, S.; Pratchett, A.G.

1989-12-01

A suite of three programmes has been developed to model the ruthenium decontamination performance of a vitrification plant off-gas condenser. The stages of the model are: condensation of water vapour, NO x absorption in the condensate, RuO 4 absorption in the condensate. Juxtaposition of these stages gives a package that may be run on an IBM-compatible desktop PC. Experimental work indicates that the criterion [HNO 2 ] > 10 [RuO 4 ] used to determine RuO 4 destruction in solution is probably realistic under condenser conditions. Vapour pressures of RuO 4 over aqueous solutions at 70 o -90 o C are slightly lower than the values given by extrapolating the ln K p vs. T -1 relation derived from lower temperature data. (author)

Independent dose per monitor unit review of eight U.S.A. proton treatment facilities

International Nuclear Information System (INIS)

Moyers, M. F.; Ibbott, G. S.; Grant, R. L.; Summers, P. A.; Followill, D. S.

2014-01-01

Purpose: Compare the dose per monitor unit at different proton treatment facilities using three different dosimetry methods. Methods: Measurements of dose per monitor unit were performed by a single group at eight facilities using 11 test beams and up to six different clinical portal treatment sites. These measurements were compared to the facility reported dose per monitor unit values. Results: Agreement between the measured and reported doses was similar using any of the three dosimetry methods. Use of the ICRU 59 N D,w based method gave results approximately 3% higher than both the ICRU 59 N X and ICRU 78 (TRS-398) N D,w based methods. Conclusions: Any single dosimetry method could be used for multi-institution trials with similar conformity between facilities. A multi-institutional trial could support facilities using both the ICRU 59 N X based and ICRU 78 (TRS-398) N D,w based methods but use of the ICRU 59 N D,w based method should not be allowed simultaneously with the other two until the difference is resolved

Maintenance of order in a moving strong condensate

International Nuclear Information System (INIS)

Whitehouse, Justin; Costa, André; Blythe, Richard A; Evans, Martin R

2014-01-01

We investigate the conditions under which a moving condensate may exist in a driven mass transport system. Our paradigm is a minimal mass transport model in which n − 1 particles move simultaneously from a site containing n > 1 particles to the neighbouring site in a preferred direction. In the spirit of a zero-range process the rate u(n) of this move depends only on the occupation of the departure site. We study a hopping rate u(n) = 1 + b/n α numerically and find a moving strong condensate phase for b > b c (α) for all α > 0. This phase is characterised by a condensate that moves through the system and comprises a fraction of the system's mass that tends to unity. The mass lost by the condensate as it moves is constantly replenished from the trailing tail of low occupancy sites that collectively comprise a vanishing fraction of the mass. We formulate an approximate analytical treatment of the model that allows a reasonable estimate of b c (α) to be obtained. We show numerically (for α = 1) that the transition is of mixed order, exhibiting a discontinuity in the order parameter as well as a diverging length scale as b↘b c . (paper)

Fuel conditioning facility electrorefiner cadmium vapor trap operation

International Nuclear Information System (INIS)

Vaden, D. E.

1998-01-01

Processing sodium-bonded spent nuclear fuel at the Fuel Conditioning Facility at Argonne National Laboratory-West involves an electrometallurgical process employing a molten LiCl-KCl salt covering a pool of molten cadmium. Previous research has shown that the cadmium dissolves in the salt as a gas, diffuses through the salt layer and vaporizes at the salt surface. This cadmium vapor condenses on cool surfaces, causing equipment operation and handling problems. Using a cadmium vapor trap to condense the cadmium vapors and reflux them back to the electrorefiner has mitigated equipment problems and improved electrorefiner operations

Estimation of marginal costs at existing waste treatment facilities.

Science.gov (United States)

Martinez-Sanchez, Veronica; Hulgaard, Tore; Hindsgaul, Claus; Riber, Christian; Kamuk, Bettina; Astrup, Thomas F

2016-04-01

address and include costs in existing waste facilities in decision-making may unintendedly lead to higher overall costs at societal level. To avoid misleading conclusions, economic assessment of alternative SWM solutions should not only consider potential costs associated with alternative treatment but also include marginal costs associated with existing facilities. Copyright © 2016 Elsevier Ltd. All rights reserved.

Development of Flow Boiling and Condensation Experiment on the International Space Station- Normal and Low Gravity Flow Boiling Experiment Development and Test Results

Science.gov (United States)

Nahra, Henry K.; Hall, Nancy R.; Hasan, Mohammad M.; Wagner, James D.; May, Rochelle L.; Mackey, Jeffrey R.; Kolacz, John S.; Butcher, Robert L.; Frankenfield, Bruce J.; Mudawar, Issam;

Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Norm Stanley

2011-02-01

This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

Assessment of RELAP5/MOD3.3 condensation models for the tube bundle condensation in the PCCS of ESBWR

International Nuclear Information System (INIS)

Zhou, W.; Wolf, B.; Revankar, S.T.

2011-01-01

The passive containment condenser system (PCCS) in an ESBWR reactor consists of vertical tube bundle submerged in a large pool of water. The condensation model for the PCCS in a thermalhydraulics code RELAP5/MOD3.3 consists of the default Nusselt model and an alternate condensation model from UCB condensation correlation. An assessment of the PCCS condensation model in RELAP5/MOD3.3 was carried out using experiments conducted on a single tube and tube bundle PCCS tests at Purdue University. The experimental conditions were simulated with the default and the alternate condensation models in the REALP5/MOD3.3 beta version of the code. The default model and the UCB model (alternate model) give quite different results on condensation heat transfer for the PCCS. The default model predicts complete condensation well whereas the UCB model predicts the through flow condensation well. Based on this study it was found that none of the models in REALP5 can predict complete condensation as well as the through flow condensation well. (author)

Assessment of RELAP5/MOD3.3 condensation models for the tube bundle condensation in the PCCS of ESBWR

Energy Technology Data Exchange (ETDEWEB)

Zhou, W., E-mail: wenzzhou@cityu.edu.hk [Department of Mechanical and Biomedical Engineering, City University of Hong Kong, Hong Kong (China); Wolf, B. [Purdue University, West Lafayette, IN 47907 (United States); Revankar, S. [Purdue University, West Lafayette, IN 47907 (United States); POSTECH, Pohang (Korea, Republic of)

2013-11-15

The passive containment condenser system (PCCS) in an ESBWR reactor consists of vertical tube bundle submerged in a large pool of water. The condensation model for the PCCS in a thermalhydraulics code RELAP5/MOD3.3 consists of the default Nusselt model and an alternate condensation model from UCB condensation correlation. An assessment of the PCCS condensation model in RELAP5/MOD3.3 was carried out using experiments conducted on a single tube and tube bundle PCCS tests at Purdue University. The experimental conditions were simulated with the default and the alternate condensation models in the REALP5/MOD3.3 beta version of the code. The default model and the UCB model (alternate model) give quite different results on condensation heat transfer for the PCCS. The default model predicts complete condensation well whereas the UCB model predicts the through flow condensation well. Based on this study it was found that none of the models in REALP5 can predict complete condensation as well as the through flow condensation well.

Laboratory Studies of the Optical Properties and Condensation Processes of Cosmic Dust Grains

Science.gov (United States)

Abbas, M. M.; Craven, P. D.; Spann, J. F.; Tankosic, D.; LeClair, A.; West, E.; Sheldon, R.; Witherow, W. K.; Gallagher, D. L.; Adrian, M. L.

2002-01-01

A laboratory facility for conducting a variety of experiments on single isolated dust particles of astrophysical interest levitated in an electrodynamics balance has been developed at NASA/Marshall Space Flight Center. The objective of the research is to employ this experimental technique for studies of the physical and optical properties of individual cosmic dust grains of 0.1-100 micron size in controlled pressure/temperatures environments simulating astrophysical conditions. The physical and optical properties of the analogs of interstellar and interplanetary dust grains of known composition and size distribution will be investigated by this facility. In particular, we will carry out three classes of experiments to study the micro-physics of cosmic dust grains. (1) Charge characteristics of micron size single dust grains to determine the photoelectric efficiencies, yields, and equilibrium potentials when exposed to UV radiation. (2) Infrared optical properties of dust particles (extinction coefficients and scattering phase functions) in the 1-30 micron region using infrared diode lasers and measuring the scattered radiation. (3) Condensation experiments to investigate the condensation of volatile gases on colder nucleated particles in dense interstellar clouds and lower planetary atmospheres. The condensation experiments will involve levitated nucleus dust grains of known composition and initial mass (or m/q ratio), cooled to a temperature and pressure (or scaled pressure) simulating the astrophysical conditions, and injection of a volatile gas at a higher temperature from a controlled port. The increase in the mass due to condensation on the particle will be monitored as a function of the dust particle temperature and the partial pressure of the injected volatile gas. The measured data will permit determination of the sticking coefficients of volatile gases and growth rates of dust particles of astrophysical interest. Some preliminary results based on

The DRAGON aerosol research facility to study aerosol behaviour for reactor safety applications

International Nuclear Information System (INIS)

Suckow, Detlef; Guentay, Salih

2008-01-01

During a severe accident in a nuclear power plant fission products are expected to be released in form of aerosol particles and droplets. To study the behaviour of safety relevant reactor components under aerosol loads and prototypical severe accident conditions the multi-purpose aerosol generation facility DRAGON is used since 1994 for several projects. DRAGON can generate aerosol particles by the evaporation-condensation technique using a plasma torch system, fluidized bed and atomization of particles suspended in a liquid. Soluble, hygroscopic aerosol (i.e. CsOH) and insoluble aerosol particles (i.e. SnO 2 , TiO 2 ) or mixtures of them can be used. DRAGON uses state-of-the-art thermal-hydraulic, data acquisition and aerosol measurement techniques and is mainly composed of a mixing chamber, the plasma torch system, a steam generator, nitrogen gas and compressed air delivery systems, several aerosol delivery piping, gas heaters and several auxiliary systems to provide vacuum, coolant and off-gas treatment. The facility can be operated at system pressure of 5 bars, temperatures of 300 deg. C, flow rates of non-condensable gas of 900 kg/h and steam of 270 kg/h, respectively. A test section under investigation is attached to DRAGON. The paper summarizes and demonstrates with the help of two project examples the capabilities of DRAGON for reactor safety studies. (authors)

Design and Shielding of Radiotherapy Treatment Facilities; IPEM Report 75, 2nd Edition

Science.gov (United States)

Horton, Patrick; Eaton, David

2017-07-01

Design and Shielding of Radiotherapy Treatment Facilities provides readers with a single point of reference for protection advice to the construction and modification of radiotherapy facilities. The book assembles a faculty of national and international experts on all modalities including megavoltage and kilovoltage photons, brachytherapy and high-energy particles, and on conventional and Monte Carlo shielding calculations. This book is a comprehensive reference for qualified experts and radiation-shielding designers in radiation physics and also useful to anyone involved in the design of radiotherapy facilities.

Treatment compliance and challenges among tuberculosis patients across selected health facilities in Osun State Nigeria.

Science.gov (United States)

Ajao, K O; Ogundun, O A; Afolabi, O T; Ojo, T O; Atiba, B P; Oguntunase, D O

2014-12-01

Tuberculosis (TB) is a major public health problem in the world and Africa has approximately one quarter of the world's cases. One of the greatest challenges facing most TB programmes is the non-compliance to TB treatment among TB patients. This study aimed at determining the challenges of management of tuberculosis (TB) across selected Osun State health facilities. The study employed a descriptive cross-sectional design. A semi-structured questionnaire was used to collect data from 102 TB patients in the health facilities. The instrument measured socio-demographic variables, patient related factors, socio-economic variables, health care system related factors to TB disease and treatment. Data were analysed and summarized using descriptive and inferential statistics. Statistical significance was placed at p facilities (χ2 = 21.761, p facility and patient-related factors were largely responsible.

Operation technology of the ventilation system of the radioactive waste treatment facility(II) - Design and operation note

Energy Technology Data Exchange (ETDEWEB)

Lee, K. M.; Lee, B. C.; Bae, S. M. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-12-01

As the radioactive waste treatment work, such as compaction and/or solidification of wastes, are done directly by the workers in the Radioactive Waste Treatment Facility, the reasonable design and operation of the ventilation system is essential. In this report, the design criteria and specification of the ventilation equipment, system operation method are described for the effective design and operation of ventilation system in the radioactive waste treatment facility. And the anti-vibration work which was done in the Radioactive Waste Treatment Facility in KAERI to reduce the effect of vibration due to the continuous operation of big rotational equipment, the intake fans and the exhaust fans, are described in the report. 11 refs., 10 figs., 12 tabs. (Author)

Infection control challenges in deployed US military treatment facilities.

Science.gov (United States)

Hospenthal, Duane R; Crouch, Helen K

2009-04-01

Personnel sustaining combat-related injuries in current overseas conflicts continue to have their care complicated by infections caused by multidrug-resistant organisms, including Acinetobacter, Klebsiella, and Pseudomonas. Although presumed to be due to multiple factors both within and outside of the combat theater, concern has been raised about the difficulties in establishing and maintaining standard infection control (IC) practices in deployed medical treatment facilities and in the evacuation of the injured back to the United States. Level III facilities (hospitals capable of holding patients >72 hours) in Iraq and Afghanistan and the evacuation system from Iraq to the continental US were reviewed by an expert IC-infectious disease team. All reviewed facilities had established IC programs, but these were staffed by personnel with limited IC experience, often without perceived adequate time dedicated to perform their duties, and without uniform levels of command emphasis or support. Proper hand hygiene between patients was not always ideal. Isolation and cohorting of patients to decrease multidrug-resistant organism colonization and infection varied among facilities. Review of standard operating procedures found variability among institutions and in quality of these documents. Application of US national and theater-specific guidelines and of antimicrobial control measures also varied among facilities. Effective IC practices are often difficult to maintain in modern US hospitals. In the deployed setting, with ever-changing personnel in a less than optimal practice environment, IC is even more challenging. Standardization of practice with emphasis on the basics of IC practice (e.g., hand hygiene and isolation procedures) needs to be emplaced and maintained in the deployed setting.

The Effect of Capillary Number on a Condensate Blockage in Gas Condensate Reservoirs

OpenAIRE

Saifon DAUNGKAEW; Alain C GRINGARTEN

2004-01-01

In the petroleum industry, gas condensate reservoirs are becoming more common as exploration targets. However, there is a lack of knowledge of the reservoir behaviour mainly due to its complexity in the near wellbore region, where two phases, i.e. reservoir gas and condensate coexist when the wellbore pressure drops below the dew point pressure. The condensation process causes a reduction of the gas productivity (1). It has been reported in the literature that there is an increasing gas mobil...

Flow Boiling and Condensation Experiment (FBCE) for the International Space Station

Science.gov (United States)

Mudawar, Issam; O'Neill, Lucas; Hasan, Mohammad; Nahra, Henry; Hall, Nancy; Balasubramaniam, R.; Mackey, Jeffrey

2016-01-01

An effective means to reducing the size and weight of future space vehicles is to replace present mostly single-phase thermal management systems with two-phase counterparts. By capitalizing upon both latent and sensible heat of the coolant rather than sensible heat alone, two-phase thermal management systems can yield orders of magnitude enhancement in flow boiling and condensation heat transfer coefficients. Because the understanding of the influence of microgravity on two-phase flow and heat transfer is quite limited, there is an urgent need for a new experimental microgravity facility to enable investigators to perform long-duration flow boiling and condensation experiments in pursuit of reliable databases, correlations and models. This presentation will discuss recent progress in the development of the Flow Boiling and Condensation Experiment (FBCE) for the International Space Station (ISS) in collaboration between Purdue University and NASA Glenn Research Center. Emphasis will be placed on the design of the flow boiling module and on new flow boiling data that were measured in parabolic flight, along with extensive flow visualization of interfacial features at heat fluxes up to critical heat flux (CHF). Also discussed a theoretical model that will be shown to predict CHF with high accuracy.

Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser

Energy Technology Data Exchange (ETDEWEB)

Papini, Davide, E-mail: davide.papini@psi.ch; Adamsson, Carl; Andreani, Michele; Prasser, Horst-Michael

2014-10-15

Highlights: • Code comparison on the performance of a Passive Containment Condenser. • Simulation of separate effect tests with pure steam and non-condensable gases. • Role of the secondary side and accuracy of pool boiling models are discussed. • GOTHIC and TRACE predict the experimental performance with slight underestimation. • Recirculatory flow pattern with injection of light non-condensable gas is inferred. - Abstract: Typical passive safety systems for ALWRs (Advanced Light Water Reactors) rely on the condensation of steam to remove the decay heat from the core or the containment. In the present paper the three-dimensional containment code GOTHIC and the one-dimensional system code TRACE are compared on the calculation of a variety of phenomena characterizing the response of a passive condenser submerged in a boiling pool. The investigation addresses the conditions of interest for the Passive Containment Cooling System (PCCS) proposed for the ESBWR (Economic Simplified Boiling Water Reactor). The analysis of selected separate effect tests carried out on a PCC (Passive Containment Condenser) unit in the PANDA large-scale thermal-hydraulic facility is presented to assess the code predictions. Both pure steam conditions (operating pressure of 3 bar, 6 bar and 9 bar) and the effect on the condensation heat transfer of non-condensable gases heavier than steam (air) and lighter than steam (helium) are considered. The role of the secondary side (pool side) heat transfer on the condenser performance is examined too. In general, this study shows that both the GOTHIC and TRACE codes are able to reasonably predict the heat transfer capability of the PCC as well as the influence of non-condensable gas on the system. A slight underestimation of the condenser performance is obtained with both codes. For those tests where the experimental and simulated efficiencies agree better the possibility of compensating errors among different parts of the heat transfer

Transition from condensation-induced counter-current flow to dispersed flow

International Nuclear Information System (INIS)

Gale, J.; Tiselj, I.

2004-01-01

Model of transition from the horizontally stratified condensation-induced counter-current flow to slug flow has been analyzed with computer code WAHA and compared to the experimental data obtained in the steamline of the PMK2 test facility of Hungarian Atomic Energy Institute. The experiment was performed in the steamline initially filled with hot vapor that was gradually flooded with cold liquid. Successful simulation of the condensation-induced water hammer that follows the transition, requires accurate description of the horizontally stratified and slug flow regimes and criteria for transition between both flow regimes. Current version of the WAHA code, not verified for the condensation induced type of the water hammer, predicts the water-hammer pressure peak that exceeds 600 bar, while the measured pressure is p m = 170 ± 50 bar. Sensitivity analysis of the inter-phase exchange terms and transition conditions, pointed to the most important closure relations for heat, mass and momentum transfer. The main conclusion of the analysis is large uncertainty of the simulations: minor modification of the crucial correlations can lead to a severe water-hammer in one case, or to the 'calm' transient without pressure peaks in the other case. Large uncertainty is observed in experiments. The same simulation was performed also with RELAP5 code. However, no water hammer was predicted. (author)

Engineering report for interim solids removal modifications of the Steam Plant Wastewater Treatment Facility

International Nuclear Information System (INIS)

1995-04-01

The Steam Plant Wastewater Treatment Facility (SPWTF) treats wastewater from the Y-12 Plant coal yard, steam plant, and water demineralizer facility. The facility is required to comply with National Pollutant Discharge Elimination System (NPDES) standards prior to discharge to East Fork Poplar Creek (EFPC). The existing facility was designed to meet Best Available Technology (BAT) standards and has been in operation since 1988. The SPWTF has had intermittent violations of the NPDES permit primarily due to difficulties in complying with the limit for total iron of 1.0 ppM. A FY-1997 Line Item project, SPWTF Upgrades, is planned to improve the capabilities of the SPWTF to eliminate non-compliances with the permit limits. The intent of the Interim Solids Removal Modification project is to improve the SPWTF effluent quality and to provide pilot treatment data to assist in the design and implementation of the SPWTF Upgrades Line Item Project

Ghost condensate and generalized second law

International Nuclear Information System (INIS)

Mukohyama, Shinji

2009-01-01

Dubovsky and Sibiryakov recently proposed a scenario in which particles of different species propagate with different speeds due to their direct couplings to ghost condensate. It was argued that this extended version of ghost condensate allows a gedanken experiment leading to violation of the generalized second law. However, in the original ghost condensate scenario, difference in propagation speeds is suppressed by M 2 /M Pl 2 , where M is the order parameter of spontaneous Lorentz breaking and M Pl is the Planck scale. In this case the energy transfer necessary for the gedanken experiment is so slow that the timescale of decrease of entropy, if any, is always longer than the Jeans timescale of ghost condensate. Hence the generalized second law is not violated by the gedanken experiment in the original ghost condensate scenario. This conclusion trivially extends to gauged ghost condensation by taking into account accretion of gauged ghost condensate into a black hole.

Black holes in the ghost condensate

International Nuclear Information System (INIS)

Mukohyama, Shinji

2005-01-01

We investigate how the ghost condensate reacts to black holes immersed in it. A ghost condensate defines a hypersurface-orthogonal congruence of timelike curves, each of which has the tangent vector u μ =-g μν ∂ ν φ. It is argued that the ghost condensate in this picture approximately corresponds to a congruence of geodesics. In other words, the ghost condensate accretes into a black hole just like a pressureless dust. Correspondingly, if the energy density of the ghost condensate at large distance is set to an extremely small value by cosmic expansion then the late-time accretion rate of the ghost condensate should be negligible. The accretion rate remains very small even if effects of higher derivative terms are taken into account, provided that the black hole is sufficiently large. It is also discussed how to reconcile the black-hole accretion with the possibility that the ghost condensate might behave like dark matter

200 Area effluent treatment facility process control plan 98-02

International Nuclear Information System (INIS)

Le, E.Q.

1998-01-01

This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP)

Facility-Based treatment of under five diarrhoea in Cross River State ...

African Journals Online (AJOL)

2015-06-29

Jun 29, 2015 ... based diarrhoea treatment strategies and guidelines by health care professional at the facility level will go a long way in improving .... p-value. Oral rehydration solution alone or given with Zinc1. 28. (10.0%). 12 (13.2%).

Gaps in the implementation of antenatal syphilis detection and treatment in health facilities across sub-Saharan Africa.

Science.gov (United States)

Kanyangarara, Mufaro; Walker, Neff; Boerma, Ties

2018-01-01

Syphilis in pregnancy is an under-recognized public health problem, especially in sub-Saharan Africa which accounts for over 60% of the global burden of syphilis. If left untreated, more than half of maternal syphilis cases will result in adverse pregnancy outcomes including stillbirth and fetal loss, neonatal death, prematurity or low birth weight, and neonatal infections. Achieving universal coverage of antenatal syphilis screening and treatment has been the focus of the global campaign for the elimination of mother-to-child transmission of syphilis. However, little is known about the availability of antenatal syphilis screening and treatment across sub-Saharan Africa. The objective of this study was to estimate the 'likelihood of appropriate care' for antenatal syphilis screening and treatment by analyzing health facility surveys and household surveys conducted from 2010 to 2015 in 12 sub-Saharan African countries. In this secondary data analysis, we linked indicators of health facility readiness to provide antenatal syphilis detection and treatment from Service Provision Assessments (SPAs) and Service Availability and Readiness Assessments (SARAs) to indicators of ANC use from the Demographic and Health Surveys (DHS) to compute estimates of the 'likelihood of appropriate care'. Based on data from 5,593 health facilities that reported offering antenatal care (ANC) services, the availability of syphilis detection and treatment in ANC facilities ranged from 2% to 83%. The availability of syphilis detection and treatment was substantially lower in ANC facilities in West Africa compared to the other sub-regions. Levels of ANC attendance were high (median 94.9%), but only 27% of ANC attendees initiated care at less than 4 months gestation. We estimated that about one in twelve pregnant women received ANC early (<4 months) at a facility ready to provide syphilis detection and treatment (median 8%, range 7-32%). The largest implementation bottleneck identified was low

Facility-level, state, and financial factors associated with changes in the provision of smoking cessation services in US substance abuse treatment facilities: Results from the National Survey of Substance Abuse Treatment Services 2006 to 2012.

Science.gov (United States)

Cohn, Amy; Elmasry, Hoda; Niaura, Ray

2017-06-01

Cigarette smoking is common among patients in substance abuse treatment. Tobacco control programs have advocated for integrated tobacco dependence treatment into behavioral healthcare, including within substance abuse treatment facilities (SATFs) to reduce the public health burden of tobacco use. This study used data from seven waves (2006 to 2012) of the National Survey of Substance Abuse Treatment Services (n=94,145) to examine state and annual changes in the provision of smoking cessation services within US SATFs and whether changes over time could be explained by facility-level (private vs public ownership, receipt of earmarks, facility admissions, acceptance of government insurance) and state-level factors (cigarette tax per pack, smoke free policies, and percent of CDC recommended tobacco prevention spending). Results showed that the prevalence of SATFs offering smoking cessation services increased over time, from 13% to 65%. The amount of tax per cigarette pack, accepting government insurance, government (vs private) ownership, facility admissions, and CDC recommended tobacco prevention spending (per state) were the strongest correlates of the provision of smoking cessation programs in SATFs. Facilities that received earmarks were less likely to provide cessation services. Adult smoking prevalence and state-level smoke free policies were not significant correlates of the provision of smoking cessation services over time. Policies aimed at increasing the distribution of tax revenues to cessation services in SATFs may offset tobacco-related burden among those with substance abuse problems. Copyright © 2017. Published by Elsevier Inc.

Operational experience at the Sludge Treatment Facility

International Nuclear Information System (INIS)

Sy, D.J.

1987-01-01

The Sludge Treatment Facility (STF) at the Oak Ridge Gaseous Diffusion Plant has been in operation since April 1987. The facility was designed to encapsulate hazardous sludge wastes in a cement matrix. Fixation will allow the waste to meet or exceed applicable compressive strength and leachability requirements. Thus, the grout mixture complies with the Resource Conservation and Recovery Act (RCRA) guidelines as a nonhazardous waste. The grout mixture is based upon a recipe formulation developed after several years of waste stream characterization and formulation studies. The wastes to be treated at the STF are wastes impounded in two ponds. The ponds have a combined capacity of 4.5 million gallons of sludge. The sludge is transferred from the ponds to a 15,000-gallon capacity storage tank by the use of a dredge. The grout mixture recipe dictates the amount of sludge, cement, fly ash, and admixture required for weighing per batch. All ingredients are weighed and then transferred to a tilt or high energy mixer for mixing. The grout mixture is then transferred to 89- or 96-gallon steel drums. The drums are placed in a storage yard designed for a point source discharge from the yard

Physics of condensed matter

CERN Document Server

Misra, Prasanta K

2012-01-01

Physics of Condensed Matter is designed for a two-semester graduate course on condensed matter physics for students in physics and materials science. While the book offers fundamental ideas and topic areas of condensed matter physics, it also includes many recent topics of interest on which graduate students may choose to do further research. The text can also be used as a one-semester course for advanced undergraduate majors in physics, materials science, solid state chemistry, and electrical engineering, because it offers a breadth of topics applicable to these majors. The book be

Pion condensation and neutron star dynamics

International Nuclear Information System (INIS)

Kaempfer, B.

1983-01-01

The question of formation of pion condensate via a phase transition in nuclear matter, especially in the core of neutron stars is reviewed. The possible mechanisms and the theoretical restrictions of pion condensation are summarized. The effects of ultradense equation of state and density jumps on the possible condensation phase transition are investigated. The possibilities of observation of condensation process are described. (D.Gy.)

Legal problems of waste treatment in German atomic energy facilities

International Nuclear Information System (INIS)

Pfaffelhuber, J.K.

1980-01-01

The execution of the strategies of waste treatment and disposal calls for the laws and regulations on the obligations of the owners of equipments and facilities and of the state for securing safety and the final elimination of radioactive wastes, which are defined mainly in Article 9 of Atomgesetz and Section 2 (Article 44 - 48) of the order on protection from radiation. The owners of equipments and facilities of atomic energy technology shall limit the emission of radiation to about 6% of internationally permissible values, avoid uncontrolled emission without fail, inspect emission and submit reports yearly to government offices. The owners have attention obligations to utilize harmlessly produced radioactive residues and the expanded or dismantled parts of radioactive equipments or to eliminate orderly such things as radioactive wastes, only when such utilization is unable technically or economically, or not adequate under the protection aims of Atomgesetz. The possessors of radioactive wastes shall deliver the wastes to the accumulation places of provinces for intermediate storage, to the facilities of the Federal Republic for securing safety or final storage, or the facilities authorized by government offices for the elimination of radioactive wastes. Provinces shall install the accumulation places for the intermediate storage of radioactive wastes produced in their territories, and the Federal Republic shall set up the facilities for securing safety and the final elimination of radioactive wastes (Article 9, Atomgesetz). (Okada, K.)

Experiments with the HORUS-II test facility

Energy Technology Data Exchange (ETDEWEB)

Alt, S.; Lischke, W. [Univ. for Applied Sciences Zittau/Goerlitz, Zittau (Germany). Dept. of Nuclear Engineering

1997-12-31

Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA`s fourth phase at the original plant. 4 refs.

Experiments with the HORUS-II test facility

Energy Technology Data Exchange (ETDEWEB)

Alt, S; Lischke, W [Univ. for Applied Sciences Zittau/Goerlitz, Zittau (Germany). Dept. of Nuclear Engineering

1998-12-31

Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA`s fourth phase at the original plant. 4 refs.

Experiments with the HORUS-II test facility

International Nuclear Information System (INIS)

Alt, S.; Lischke, W.

1997-01-01

Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA's fourth phase at the original plant

Air Emissions Sampling from Vacuum Thermal Desorption for Mixed Wastes Designated with a Combustion Treatment Code for the Energy Solutions LLC Mixed Waste Facility

International Nuclear Information System (INIS)

Christensen, M.E.; Willoughby, O.H.

2009-01-01

EnergySolutions LLC is permitted by the State of Utah to treat organically-contaminated Mixed Waste by a vacuum thermal desorption (VTD) treatment process at its Clive, Utah treatment, storage, and disposal facility. The VTD process separates organics from organically-contaminated waste by heating the material in an inert atmosphere, and captures them as concentrated liquid by condensation. The majority of the radioactive materials present in the feed to the VTD are retained with the treated solids; the recovered aqueous and organic condensates are not radioactive. This is generally true when the radioactivity is present in solid form such as inorganic salts, metals or metallic oxides. The exception is when volatile radioactive materials are present such as radon gas, tritium, or carbon-14 organic chemicals. Volatile radioactive materials are a small fraction of the feed material. On August 28, 2006, EnergySolutions submitted a request to the USEPA for a variance to the Land Disposal Restrictions (LDR) standards for wastes designated with the combustion treatment code (CMBST). The final rule granting a site specific treatment variance was effective June 13, 2008. This variance is an alternative treatment standard to treatment by CMBST required for these wastes under USEPA's rules. The State of Utah provides oversight of the VTD processing operations. A demonstration test for treating CMBST-coded wastes was performed on April 29, 2008 through May 1, 2008. Three separate process cycles were conducted during this test. Both solid/liquid samples and emission samples were collected each day during the demonstration test. To adequately challenge the unit, feed material was spiked with trichloroethylene, o-cresol, dibenzofuran, and coal tar. Emission testing was conducted by EnergySolutions' emissions test contractor and sampling for radioactivity within the off-gas was completed by EnergySolutions' Health Physics department. This report discusses the emission testing

Experimental and numerical investigations on the direct contact condensation phenomenon in horizontal flow channels and its implications in nuclear safety

Energy Technology Data Exchange (ETDEWEB)

Ceuca, Sabin Cristian [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Laurinavicius, Darius [Lithuanian Energy Institute, Kaunas (Lithuania)

2016-11-15

The complex direct contact condensation phenomenon is investigated in horizontal flow channels both experimentally and numerically with special emphasis on its implications on safety assessment studies. Under certain conditions direct contact condensation can act as the driving force for the water hammer phenomenon with potentially local devastating results, thus posing a threat to the integrity of the affected NPP components. New experimental results of in-depth analysis of the direct contact condensation phenomena obtained in Kaunas at the Lithuanian Energy Institute will be presented. The German system code ATHLET employing for the calculation of the heat transfer coefficient a mechanistic model accounting for two different eddy length scales, combined with the interfacial area transport equation will be assessed against condensation induced water hammer experimental data from the integral thermal-hydraulic experimental facility PMK-2, located at the KFKI Atomic Energy Research Institute in Budapest Hungary.

University-based user facilities: lessons from Tantalus and Aladdin

International Nuclear Information System (INIS)

Huber, D.L.

1985-01-01

The establishment of university-based user facilities is a relatively new development in the federal funding of research in condensed matter science. Because the Synchrotron Radiation Center (SRC) has been a pioneer user facility, a certain degree of experience, both good and bad, has been acquired in the construction and operation of university-based facilities for synchrotron-related research. The history of SRC is discussed and some of the general lessons learned in the area of advanced planning are outlined. No attempt is made to be either definitive or exhaustive. In the present context, a university-based user facility is understood to be a dedicated facility under direct university control where a majority of the users come from outside the local university community

MELCOR simulation of steam condensation effect on hydrogen behavior in THAI HM-2 experiment

Energy Technology Data Exchange (ETDEWEB)

Lee, Seongnyeon; Lee, Jung-Jae; Cho, Yong-Jin [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Sung Joong [Hanyang University, Seoul (Korea, Republic of)

2015-10-15

In this study, MELCOR simulation was carried out for THAI HM-2 experiment of OECD. As a results, stratification of hydrogen cloud was reasonably captured in MELCOR simulation. Furthermore, the pressure from simulation results in cases where mass transfer coefficient of MELCOR condensation model was modified was good agreement with the experimental results. Containment Filtered Ventilation System (CFVS) has been introduced as facility to prevent containment failure during severe accident. However, possibility of hydrogen risk has been issued due to inflow of hydrogen, condensation and removal of steam and complicated inner structure in CFVS. Preferentially benchmark work for THAI HM-2 experiment of OECD was decided to validate the methodology before detailed assessment of hydrogen risk in CFVS. The objectives of THAI HM-2 experiment were evaluation of hydrogen behavior, verification of numerical analysis tools and so on. In this paper, therefore, MELCOR simulation was carried out in comparison with the experiment results. Additionally, steam condensation effect was considered for detailed simulation. Hydrogen concentration from MELCOR results was underestimated in comparison to the experimental results.

Continuous quality improvement in substance abuse treatment facilities: How much does it cost?

Science.gov (United States)

Hunt, Priscillia; Hunter, Sarah B; Levan, Deborah

2017-06-01

Continuous quality improvement (CQI) has grown in the U.S. since the 1970s, yet little is known about the costs to implement CQI in substance abuse treatment facilities. This paper is part of a larger group randomized control trial in a large urban county evaluating the impact of Plan-Study-Do-Act (PDSA)-CQI designed for community service organizations (Hunter, Ober, Paddock, Hunt, & Levan, 2014). Operated by one umbrella organization, each of the eight facilities of the study, four residential and four outpatient substance abuse treatment facilities, selected their own CQI Actions, including administrative- and clinical care-related Actions. Using an activity-based costing approach, we collected labor and supplies and equipment costs directly attributable to CQI Actions over a 12-month trial period. Our study finds implementation of CQI and meeting costs of this trial per facility were approximately $2000 to $10,500 per year ($4500 on average), or $10 to $60 per admitted client. We provide a description of the sources of variation in these costs, including differing intensity of the CQI Actions selected, which should help decision makers plan use of PDSA-CQI. Copyright © 2017. Published by Elsevier Inc.

Optimal design of condenser weight

International Nuclear Information System (INIS)

Zheng Jing; Yan Changqi; Wang Jianjun

2011-01-01

The condenser is an important component in nuclear power plants, which dimension and weight will effect the economical performance and the arrangement of the nuclear power plants. In this paper, the calculation model is established according to the design experience. The corresponding codes are also developed, and the sensitivity of design parameters which influence the condenser weight is analyzed. The present design optimization of the condenser, taking the weight minimization as the objective, is carried out with the self-developed complex-genetic algorithm. The results show that the reference condenser design is far from the best scheme, and also verify the feasibility of the complex-genetic algorithm. (authors)

Association Between Facility-Level Utilization of Non-pharmacologic Chronic Pain Treatment and Subsequent Initiation of Long-Term Opioid Therapy.

Science.gov (United States)

Carey, Evan P; Nolan, Charlotte; Kerns, Robert D; Ho, P Michael; Frank, Joseph W

2018-05-01

Expert guidelines recommend non-pharmacologic treatments and non-opioid medications for chronic pain and recommend against initiating long-term opioid therapy (LTOT). We examined whether veterans with incident chronic pain receiving care at facilities with greater utilization of non-pharmacologic treatments and non-opioid medications are less likely to initiate LTOT. Retrospective cohort study PARTICIPANTS: Veterans receiving primary care from a Veterans Health Administration facility with incident chronic pain between 1/1/2010 and 12/31/2015 based on either of 2 criteria: (1) persistent moderate-to-severe patient-reported pain and (2) diagnoses "likely to represent" chronic pain. The independent variable was facility-level utilization of pain-related treatment modalities (non-pharmacologic, non-opioid medications, LTOT) in the prior calendar year. The dependent variable was patient-level initiation of LTOT (≥ 90 days within 365 days) in the subsequent year, adjusting for patient characteristics. Among 1,094,569 veterans with incident chronic pain from 2010 to 2015, there was wide facility-level variation in utilization of 10 pain-related treatment modalities, including initiation of LTOT (median, 16%; range, 5-32%). Veterans receiving care at facilities with greater utilization of non-pharmacologic treatments were less likely to initiate LTOT in the year following incident chronic pain. Conversely, veterans receiving care at facilities with greater non-opioid and opioid medication utilization were more likely to initiate LTOT; this association was strongest for past year facility-level LTOT initiation (adjusted rate ratio, 2.10; 95% confidence interval, 2.06-2.15, top vs. bottom quartile of facility-level LTOT initiation in prior calendar year). Facility-level utilization patterns of non-pharmacologic, non-opioid, and opioid treatments for chronic pain are associated with subsequent patient-level initiation of LTOT among veterans with incident chronic pain

3718-F Alkali Metal Treatment and Storage Facility Closure Plan

International Nuclear Information System (INIS)

1991-12-01

Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references

3718-F Alkali Metal Treatment and Storage Facility Closure Plan

Energy Technology Data Exchange (ETDEWEB)

None

1991-12-01

Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references.

Risk communication on the construction of radioactive waste treatment facility

International Nuclear Information System (INIS)

Okoshi, Minoru

2005-01-01

In this paper, risk communications among the Japan Radioisotope Association (JRIA), a local government and the general public which were carried out during the development process of a radioactive waste treatment facility in Takizawa Village, Iwate Prefecture are analyzed based on the articles of newspapers and the interviews with the concerned people. The analysis results show good risk communications were not carried out because of the absence of the confidence to the JRIA, decision making rules and the merits. In order to make good use of this experience for the future development of radioactive waste management facilities, the lessons learned from this case are summarized and the check lists for good risk communication are proposed. (author)

Treatment, Storage and Disposal (TSD) Corrective Action Facility Polygons, Region 9, 2015, US EPA Region 9

Data.gov (United States)

U.S. Environmental Protection Agency — RCRA Treatment, Storage and Disposal facilities (TSDs) are facilities that have treated, stored or disposed of hazardous wastes. They are required to clean up...

The physics of exciton-polariton condensates

CERN Document Server

Lagoudakis, Konstantinos

2013-01-01

In 2006 researchers created the first polariton Bose-Einstein condensate at 19K in the solid state. Being inherently open quantum systems, polariton condensates open a window into the unpredictable world of physics beyond the “fifth state of matter”: the limited lifetime of polaritons renders polariton condensates out-of-equilibrium and provides a fertile test-bed for non-equilibrium physics. This book presents an experimental investigation into exciting features arising from this non-equilibrium behavior. Through careful experimentation, the author demonstrates the ability of polaritons to synchronize and create a single energy delocalized condensate. Under certain disorder and excitation conditions the complete opposite case of coexisting spatially overlapping condensates may be observed. The author provides the first demonstration of quantized vortices in polariton condensates and the first observation of fractional vortices with full phase and amplitude characterization. Finally, this book investigate...

Pot-Economy Autooxidative Condensation of 2-Aryl-2-lithio-1,3-dithianes.

Science.gov (United States)

Vale, João R; Rimpiläinen, Tatu; Sievänen, Elina; Rissanen, Kari; Afonso, Carlos A M; Candeias, Nuno R

2018-02-16

The autoxidative condensation of 2-aryl-2-lithio-1,3-dithianes is here reported. Treatment of 2-aryl-1,3-dithianes with n-BuLi in the absence of any electrophile leads to condensation of three molecules of 1,3-dithianes and formation of highly functionalized α-thioether ketones orthothioesters in 51-89% yields upon air exposure. The method was further expanded to benzaldehyde dithioacetals, affording corresponding orthothioesters and α-thioether ketones in 48-97% yields. The experimental results combined with density functional theory studies support a mechanism triggered by the autoxidation of 2-aryl-2-lithio-1,3-dithianes to yield a highly reactive thioester that undergoes condensation with two other molecules of 2-aryl-2-lithio-1,3-dithiane.

Continuous droplet removal upon dropwise condensation of humid air on a hydrophobic micropatterned surface.

Science.gov (United States)

Zamuruyev, Konstantin O; Bardaweel, Hamzeh K; Carron, Christopher J; Kenyon, Nicholas J; Brand, Oliver; Delplanque, Jean-Pierre; Davis, Cristina E

2014-08-26

Combination of two physical phenomena, capillary pressure gradient and wettability gradient, allows a simple two-step fabrication process that yields a reliable hydrophobic self-cleaning condenser surface. The surface is fabricated with specific microscopic topography and further treatment with a chemically inert low-surface-energy material. This process does not require growth of nanofeatures (nanotubes) or hydrophilic-hydrophobic patterning of the surface. Trapezoidal geometry of the microfeatures facilitates droplet transfer from the Wenzel to the Cassie state and reduces droplet critical diameter. The geometry of the micropatterns enhances local coalescence and directional movement for droplets with diameter much smaller than the radial length of the micropatterns. The hydrophobic self-cleaning micropatterned condenser surface prevents liquid film formation and promotes continuous dropwise condensation cycle. Upon dropwise condensation, droplets follow a designed wettability gradient created with micropatterns from the most hydrophobic to the least hydrophobic end of the surface. The surface has higher condensation efficiency, due to its directional self-cleaning property, than a plain hydrophobic surface. We explain the self-actuated droplet collection mechanism on the condenser surface and demonstrate experimentally the creation of an effective wettability gradient over a 6 mm radial distance. In spite of its fabrication simplicity, the fabricated surface demonstrates self-cleaning property, enhanced condensation performance, and reliability over time. Our work enables creation of a hydrophobic condenser surface with the directional self-cleaning property that can be used for collection of biological (chemical, environmental) aerosol samples or for condensation enhancement.

Regional waste treatment facilities with underground monolith disposal for all low-heat-generating nuclear wastes

International Nuclear Information System (INIS)

Forsberg, C.W.

1982-01-01

An alternative system for treatment and disposal of all ''low-heat-generating'' nuclear wastes from all sources is proposed. The system, Regional Waste Treatment Facilities with Underground Monolith Disposal (RWTF/UMD), integrates waste treatment and disposal operations into single facilities at regional sites. Untreated and/or pretreated wastes are transported from generation sites such as reactors, hospitals, and industries to regional facilities in bulk containers. Liquid wastes are also transported in bulk after being gelled for transport. The untreated and pretreated wastes are processed by incineration, crushing, and other processes at the RWTF. The processed wastes are mixed with cement. The wet concrete mixture is poured into large low-cost, manmade caverns or deep trenches. Monolith dimensions are from 15 to 25 m wide, and 20 to 60 m high and as long as required. This alternative waste system may provide higher safety margins in waste disposal at lower costs

Financing CHP Projects at Wastewater Treatment Facilities with Clean Water State Revolving Funds

Science.gov (United States)

This factsheet provides information about CHP at wastewater treatment facilities, including applications, financial challenges, and financial opportunities, such as the Clean Water State Revolving Fund.

Failure analysis at a 2 kW helium liquefaction facility; Fehleranalyse bei einer 2kW- Heliumverfluessigungsanlage

Energy Technology Data Exchange (ETDEWEB)

Klenk, Rafael; Bobien, Steffen; Neumann, Holger [KIT Campus Nord, Eggenstein-Leopoldshafen (Germany). Bereich Kryotechnik

2016-07-01

At the Institute for Technical Physics of the KIT Campus Nord helium is cooled respectively liquefied by means of the Claude process. This process is beside the Brayton and Joule-Thomson process meanwhile a standard process for the liquefaction of helium. As example here a 2 kW low-temperature helium facility shall be evaluated by means of different, superordinated failure sources. This consists of condensers, heat exchangers, expansion turbines and a Joule-Thomson valve. The facility respectively component failures are divided in failures of the condenser, turbine units and failures by external factors. For this entries of the last twelve years are token. This listing shall give information about repeating events, so that here directed facility improvements can be token up.

An integrated approach to steam condensation studies inside reactor containments: A review

Energy Technology Data Exchange (ETDEWEB)

Yadav, Mahesh Kumar [Department of Mechanical Engineering, Indian Institute of Technology Kanpur, 208016 (India); Khandekar, Sameer, E-mail: samkhan@iitk.ac.in [Department of Mechanical Engineering, Indian Institute of Technology Kanpur, 208016 (India); Sharma, Pavan K. [Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)

2016-04-15

Occurrence of severe accidents, such as the Fukushima incident in 2011, is unlikely with a probability of 10{sup −5} per reactor per year. However, such kinds of accidents have serious consequences on both, short term as well as on long term public health, environment and energy policy and security. They also adversely affect the progress of nuclear power industry. Thus, despite such a low probability of occurrence, a need arises to review the safety standards of nuclear power plants, especially in the light of the Fukushima accident. Apart from other systems, a review of thermal-hydraulics and safety system for the reactor containment is vital, as it is the last barrier to radioactive leakage. Main threats to the containment integrity include over-pressurization, not only due to steam alone, but its coupling with the possibility of local hydrogen combustion, depending on the local mixture composition of steam-air-hydrogens. It must be emphasized that steam condensation rate affects the local mixture composition and presence of hydrogen significantly deteriorates the condensation rate. This intrinsic coupling needs to be understood. In this paper, steam condensation and related issues, including basics of condensation, modeling approaches, parameters affecting condensation and experiments performed (in both separate effect and integral test facilities) are critically reviewed, in the light of coupled issues of hydrogen transport and combustion. Such studies are necessary for correlation development and/or to find out the local distribution of steam-hydrogen-air mixture within the containment to locate the possible hydrogen combustion location(s) and hence, deployment of active/passive safety systems. In addition, it is important that future studies, both experimental and numerical modeling, focus on the coupled nature of the problem in a comprehensive manner for ensuring long term safety.

Transient direct-contact condensation on liquid droplets

International Nuclear Information System (INIS)

Pasamehmetoglu, K.O.; Nelson, R.A.

1987-01-01

In this paper, direct-contact condensation on subcooled liquid droplets is studied in two parts. In the first part, simple design correlations for the condensation in a steady environment are developed based upon a conduction model. These correlations include the convective heat-transfer coefficient, condensation rate, total condensation, and the droplet-thermalization time. In the second part of the paper, the effect of a time-dependent saturation temperature on the condensation process is investigated. A rapid decrease in saturation temperature is typical of condensation environments in which the steam-supply rate is limited and condensation-induced depressurization becomes important. Design correlations are developed for condensation in an environment in which the saturation temperature decreases linearly with time. These correlations are graphically compared to the design correlations of the first part through a quasi-steady approach. The error associated with this approach is quantified as a function of the rate of change of the saturation temperature

Ground Water Monitoring Requirements for Hazardous Waste Treatment, Storage and Disposal Facilities

Science.gov (United States)

The groundwater monitoring requirements for hazardous waste treatment, storage and disposal facilities (TSDFs) are just one aspect of the Resource Conservation and Recovery Act (RCRA) hazardous waste management strategy for protecting human health and the

Improving the thermodynamic efficiency of steam turbine condensers with partial tube replacement and an advanced tube bundle design

International Nuclear Information System (INIS)

Drosdziok, A.; Zorner, W.

1989-01-01

Many different problems have been experienced with power plant condensers all over the world. It has become apparent that plant availability and cost-effectiveness are significantly influenced by the thermodynamic design of the condensers and the materials selected. This paper reports that by refitting older condensers in operating plants it has proven possible to improve thermodynamic efficiency by changing the tube bundle design. In conjunction with the replacement of the cooper-bearing tubing in these condensers, which became necessary because of the introduction of high AVT (All Volatile Treatment) conditioning in the secondary circuit, it has generally been possible to fulfil the requirements imposed on the condensers without a deterioration of plant efficiency. By experience, best results have been obtained by replacing the condenser bundle with an advanced tube bundle design. Apart from solving all problems, this further improves the thermodynamic efficiency of the condensers. In nuclear power plants constructed by the Siemens KWU Group the condensers are tailored to present-day requirements

Computations for a condenser. Experimental results

International Nuclear Information System (INIS)

Walden, Jean.

1975-01-01

Computations for condensers are presented with experimental results. The computations are concerned with the steam flux at the condenser input, and inside the tube bundle. Experimental results are given for the flux inside the condenser sleeve and the flow passing through the tube bundle [fr

Charge Screening in a Charged Condensate

International Nuclear Information System (INIS)

Gabadadze, Gregory; Rosen, Rachel A.

2009-01-01

We consider a highly dense system of helium-4 nuclei and electrons in which the helium-4 nuclei have condensed. We present the condensation mechanism in the framework of low energy effective field theory and discuss the screening of electric charge in the condensate.

Polariton condensates

International Nuclear Information System (INIS)

Snoke, David; Littlewood, Peter

2010-01-01

Most students of physics know about the special properties of Bose-Einstein condensates (BECs) as demonstrated in the two best-known examples: superfluid helium-4, first reported in 1938, and condensates of trapped atomic gases, first observed in 1995. (See the article by Wolfgang Ketterle in PHYSICS TODAY, December 1999, page 30.) Many also know that superfluid 3 He and superconducting metals contain BECs of fermion pairs. An underlying principle of all those condensed-matter systems, known as quantum fluids, is that an even number of fermions with half-integer spin can be combined to make a composite boson with integer spin. Such composite bosons, like all bosons, have the property that below some critical temperature--roughly the temperature at which the thermal de Broglie wavelength becomes comparable to the distance between the bosons--the total free energy is minimized by having a macroscopic number of bosons enter a single quantum state and form a macroscopic, coherent matter wave. Remarkably, the effect of interparticle repulsion is to lead to quantum mechanical exchange interactions that make that state robust, since the exchange interactions add coherently.

Characterization of spacecraft humidity condensate

Science.gov (United States)

Muckle, Susan; Schultz, John R.; Sauer, Richard L.

1994-01-01

When construction of Space Station Freedom reaches the Permanent Manned Capability (PMC) stage, the Water Recovery and Management Subsystem will be fully operational such that (distilled) urine, spent hygiene water, and humidity condensate will be reclaimed to provide water of potable quality. The reclamation technologies currently baselined to process these waste waters include adsorption, ion exchange, catalytic oxidation, and disinfection. To ensure that the baseline technologies will be able to effectively remove those compounds presenting a health risk to the crew, the National Research Council has recommended that additional information be gathered on specific contaminants in waste waters representative of those to be encountered on the Space Station. With the application of new analytical methods and the analysis of waste water samples more representative of the Space Station environment, advances in the identification of the specific contaminants continue to be made. Efforts by the Water and Food Analytical Laboratory at JSC were successful in enlarging the database of contaminants in humidity condensate. These efforts have not only included the chemical characterization of condensate generated during ground-based studies, but most significantly the characterization of cabin and Spacelab condensate generated during Shuttle missions. The analytical results presented in this paper will be used to show how the composition of condensate varies amongst enclosed environments and thus the importance of collecting condensate from an environment close to that of the proposed Space Station. Although advances were made in the characterization of space condensate, complete characterization, particularly of the organics, requires further development of analytical methods.

46 CFR 56.50-35 - Condensate pumps.

Science.gov (United States)

2010-10-01

... APPURTENANCES Design Requirements Pertaining to Specific Systems § 56.50-35 Condensate pumps. Two means shall be provided for discharging the condensate from the main condenser, one of which shall be mechanically... suction from the condenser and a discharge to the feed tank, it may be accepted as an independent...

Mixed and Low-Level Treatment Facility Project

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

Mixed and Low-Level Treatment Facility Project

International Nuclear Information System (INIS)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided

Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

International Nuclear Information System (INIS)

Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

2012-01-01

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W PandT) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012

Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

Energy Technology Data Exchange (ETDEWEB)

Dorr, Kent A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Freeman-Pollard, Jhivaun R. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-11-14

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

Gravitationally Driven Wicking for Enhanced Condensation Heat Transfer.

Science.gov (United States)

Preston, Daniel J; Wilke, Kyle L; Lu, Zhengmao; Cruz, Samuel S; Zhao, Yajing; Becerra, Laura L; Wang, Evelyn N

2018-04-17

Vapor condensation is routinely used as an effective means of transferring heat or separating fluids. Filmwise condensation is prevalent in typical industrial-scale systems, where the condensed fluid forms a thin liquid film due to the high surface energy associated with many industrial materials. Conversely, dropwise condensation, where the condensate forms discrete liquid droplets which grow, coalesce, and shed, results in an improvement in heat transfer performance of an order of magnitude compared to filmwise condensation. However, current state-of-the-art dropwise technology relies on functional hydrophobic coatings, for example, long chain fatty acids or polymers, which are often not robust and therefore undesirable in industrial conditions. In addition, low surface tension fluid condensates, such as hydrocarbons, pose a unique challenge because common hydrophobic condenser coatings used to shed water (with a surface tension of 73 mN/m) often do not repel fluids with lower surface tensions (condensation heat transfer using gravitationally driven flow through a porous metal wick, which takes advantage of the condensate's affinity to wet the surface and also eliminates the need for condensate-phobic coatings. The condensate-filled wick has a lower thermal resistance than the fluid film observed during filmwise condensation, resulting in an improved heat transfer coefficient of up to an order of magnitude and comparable to that observed during dropwise condensation. The improved heat transfer realized by this design presents the opportunity for significant energy savings in natural gas processing, thermal management, heating and cooling, and power generation.

Numerical investigation of convective condensation with the presence of non-condensable gases in a vertical tube

Energy Technology Data Exchange (ETDEWEB)

Fu, Wen [Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Li, Xiaowei, E-mail: lixiaowei@tsinghua.edu.cn [Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Wu, Xinxin [Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Corradini, Michael L. [Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)

2016-02-15

Highlights: • Gas mixture convective condensation in vertical tubes were simulated using FLUENT code. • The simulation results matched well with experimental data. • The detailed velocity field and species distribution were investigated. • The suction factors predicted by CFD models were compared with the classical correlations. • The effects of air and helium on steam condensation were compared. - Abstract: Steam condensation is degraded when non-condensable gases are present. Convective condensation of steam–air mixture and steam–helium mixture in vertical tubes were simulated using the CFD code FLUENT. The condensation process was modeled by defining source terms for the mass, momentum, species and energy conservation equations. Several cases with various steam mass fractions were simulated, the results matched well with the experimental data. Detailed velocity field and species distribution were investigated. The radial velocity was clearly represented, and the suction effect was modeled, which needs to be accounted for when using the heat and mass transfer analogy theory. The Nusselt and Sherwood numbers predicted by CFD models were compared with the classical correlations, and the suction effects were analyzed. The suction effect is proportional to steam mass fraction, while the suction factor is little affected by the Reynolds number. For forced convection flow in this work, the buoyant force can be neglected, so the larger diffusion coefficient of steam–helium mixture would improve the steam condensation compared to steam–air mixture. The condensation mass fluxes of steam–helium mixture and steam–air mixture are almost the same at relatively high steam inlet molar fraction (≥90%).

The application of condensate water as an additional cooling media intermittently in condenser of a split air conditioning

Science.gov (United States)

Ardita, I. N.; Subagia, I. W. A.

2018-01-01

The condensate water produced by indoor a split air conditioning is usually not utilized and thrown away into the environment. The result of measurement shows that the temperature of condensate water produced by split air conditioning is quite low, that is 19-22 °C at the rate of 16-20 mL / min and it has PH balance. Under such conditions, Air Condensate produced by split air conditioning should still be recovered as an additional cooling medium on the condenser. This research will re-investigate the use of condensate water as an intermittent additional cooling of the condenser to increase the cooling capacity and performance of the air conditioning system. This research is done by experimental method whose implementation includes; designing and manufacturing of experimental equipment, mounting measuring tools, experimental data retrieval, data processing and yield analysis. The experimental results show that the use of condensate water as an intermittent additional cooling medium on split air conditioning condenser can increase the refrigeration effect about 2%, cooling capacity about 4% and 7% of COP system. Experimental results also show a decrease in power consumption in the system compressor about 3%

The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

Roberts, R.J.

1991-01-01

The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

A Local Condensation Analysis Representing Two-phase Annular Flow in Condenser/radiator Capillary Tubes

Science.gov (United States)

Karimi, Amir

1991-01-01

NASA's effort for the thermal environmental control of the Space Station Freedom is directed towards the design, analysis, and development of an Active Thermal Control System (ATCS). A two phase, flow through condenser/radiator concept was baselined, as a part of the ATCS, for the radiation of space station thermal load into space. The proposed condenser rejects heat through direct condensation of ATCS working fluid (ammonia) in the small diameter radiator tubes. Analysis of the condensation process and design of condenser tubes are based on the available two phase flow models for the prediction of flow regimes, heat transfer, and pressure drops. The prediction formulas use the existing empirical relationships of friction factor at gas-liquid interface. An attempt is made to study the stability of interfacial waves in two phase annular flow. The formulation is presented of a stability problem in cylindrical coordinates. The contribution of fluid viscosity, surface tension, and transverse radius of curvature to the interfacial surface is included. A solution is obtained for Kelvin-Helmholtz instability problem which can be used to determine the critical and most dangerous wavelengths for interfacial waves.

Materials science at an Advanced Hadron Facility

International Nuclear Information System (INIS)

Pynn, R.

1988-01-01

The uses of neutron scattering as a probe for condensed matter phenomena are described briefly and some arguments are given to justify the community's desire for more powerful neutron sources. Appropriate design parameters for a neutron source at an Advanced Hadron Facility are presented, and such a source is compared with other existing and planned spallation neutron sources. 5 refs

NPDES Permit for Dakota Magic Casino Wastewater Treatment Facility in North Dakota

Science.gov (United States)