CFD investigating the air ingress accident for a HTGR simulation of graphite corrosion oxidation

International Nuclear Information System (INIS)

Ferng, Y.M.; Chi, C.W.

2012-01-01

Highlights: ► A CFD model is proposed to investigate graphite oxidation corrosion in the HTR-10. ► A postulated air ingress accident is assumed in this paper. ► Air ingress flowrate is the predicted result, instead of the preset one. ► O 2 would react with graphite on pebble surface, causing the graphite corrosion. ► No fuel exposure is predicted to be occurred under the air ingress accident. - Abstract: Through a compressible multi-component CFD model, this paper investigates the characteristics of graphite oxidation corrosion in the HTR-10 core under the postulated accident of gas duct rupture. In this accident, air in the steam generator cavity would enter into the core after pressure equilibrium is achieved between the core and the cavity, which is also called as the air ingress accident. Oxygen in the air would react with graphite on pebble surface, subsequently resulting in oxidation corrosion and challenging fuel integrity. In this paper, characteristics of graphite oxidation corrosion during the air ingress accident can be reasonably captured, including distributions of graphite corrosion amount on the different cross-sections, time histories of local corrosion amount at the monitoring points and overall corrosion amount in the core, respectively. Based on the transient simulation results, the corrosion pattern and its corrosion rate would approach to the steady-state conditions as the accident continuously progresses. The total amount of graphite corrosion during a 3-day accident time is predicted to be about 31 kg with the predicted asymptotic corrosion rate. This predicted value is less than that from the previous work of Gao and Shi.

Air ingress accidents in tokamaks

International Nuclear Information System (INIS)

Jones, A.V.; Roccok, P.

1989-01-01

Accidents are considered consisting in a breach in the vacuum wall of a fusion reactor, the ingress of air into the torus and the mobilization and expulsion of activated eroded-sputtered material. Previous evaluations on NET, assuming bare plasma-facing components, have been reviewed and new estimates of the rate of material discharge and of the total fraction of discharged material are calculated, including resettlement processes. The case of graphite-tiled walls, without and with combustion, is also examined. Radiological evaluations are then performed to assess the hazard posed by the discharged material both within the NET building and outside it. (author). 14 refs.; 4 figs.; 3 tabs

Analytical support for the preparation of bundle test QUENCH-10 on air ingress

International Nuclear Information System (INIS)

Birchley, J.; Haste, T.; Homann, C.; Hering, W.

2005-07-01

Bundle test QUENCH-10 is dedicated to study air ingress with subsequent water quench during a supposed accident in a spent fuel storage tank. It was proposed by AEKI, Budapest, Hungary and was performed on 21 July 2004 in the QUENCH facility at Forschungszentrum Karlsruhe. Preparation of the test is based on common analytical work at Forschungszentrum Karlsruhe and Paul Scherrer Institut, Villigen, Switzerland, mainly with the severe accident codes SCDAP/RELAP5 and MELCOR, to derive the protocol for the essential test phases, namely pre-oxidation, air ingress and quench phase. For issues that could not be tackled by this computational work, suggestions for the test conduct were made and applied during the test. Improvements of the experimental set-up and the test conduct were suggested and largely applied. In SCDAP/RELAP5, an error was found: for thick oxide scales, the output value of the oxide scale is sensibly underestimated. For the aims of the test preparation, its consequences could be taken into account. Together with the related computational and other analytical support by the engaged institutions the test is co-financed as test QUENCH-L1 by the European Community under the Euratom Fifth Framework Programme on Nuclear Fission Safety 1998 - 2002 (LACOMERA Project, contract No. FIR1-CT2002-40158). (orig.)

Separate-effects experiments on the hydrodynamics of air ingress phenomena for the very high temperature reactor

International Nuclear Information System (INIS)

Kim, S.; Talley, J.; Yadav, M.; Ireland, A.; Bajorek, S.

2011-01-01

The present study performs scaled separate-effects experiments to investigate the hydrodynamics in the air-ingress phenomena following a Depressurized Condition Cooldown in the Very High Temperature Gas-Cooled Reactor. First, a scoping experiment using water and brine is performed. The volumetric exchange rate is measured using a hydrometer, and flow visualizations are performed. Next, Helium-air experiments are performed to obtain three-dimensional oxygen concentration transient data using an oxygen analyzer. It is found that there exists a critical density difference ratio, before which the ingress rate increases linearly with time and after which the ingress rate slows down significantly. In both the water-brine and Helium-air experiments, this critical ratio is found to be approximately 0.7. (author)

Separate-effects experiments on the hydrodynamics of air ingress phenomena for the very high temperature reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, S.; Talley, J.; Yadav, M., E-mail: skim@psu.edu [The Pennsylvania State Univ., University Park, Pennsylvania (United States); Ireland, A.; Bajorek, S. [The United States Nuclear Regulatory Commission, Washington DC (United States)

2011-07-01

The present study performs scaled separate-effects experiments to investigate the hydrodynamics in the air-ingress phenomena following a Depressurized Condition Cooldown in the Very High Temperature Gas-Cooled Reactor. First, a scoping experiment using water and brine is performed. The volumetric exchange rate is measured using a hydrometer, and flow visualizations are performed. Next, Helium-air experiments are performed to obtain three-dimensional oxygen concentration transient data using an oxygen analyzer. It is found that there exists a critical density difference ratio, before which the ingress rate increases linearly with time and after which the ingress rate slows down significantly. In both the water-brine and Helium-air experiments, this critical ratio is found to be approximately 0.7. (author)

SARNET2 benchmark on air ingress experiments QUENCH-10, -16

International Nuclear Information System (INIS)

Fernandez-Moguel, Leticia; Bals, Christine; Beuzet, Emilie; Bratfisch, Christian; Coindreau, Olivia; Hózer, Zoltan; Stuckert, Juri; Vasiliev, Alexander; Vryashkova, Petya

2014-01-01

Highlights: • Two similar QUENCH air ingress experiments were analysed with eight different codes. • Eight institutions have participated in the study. • Differences in the code were mostly small to moderate during the pre-oxidation. • Differences in the code were larger during the air phase. • Study has proven that there are physical processes that should be further studied. - Abstract: The QUENCH-10 (Q-10) and QUENCH-16 (Q-16) experiments were chosen as a SARNET2 code benchmark (SARNET2-COOL-D5.4) exercise to assess the status of modelling air ingress sequences and to compare the capabilities of the various codes used for accident analyses, specifically ATHLET-CD (GRS and RUB), ICARE-CATHARE (IRSN), MAAP (EDF), MELCOR (INRNE and PSI), SOCRAT (IBRAE), and RELAP/SCDAPSim (PSI). Both experiments addressed air ingress into an overheated core following earlier partial oxidation in steam. Q-10 was performed with extensive preoxidation, moderate/high air flow rate and high temperatures at onset of reflood (max T pct = 2200 K), while Q-16 was performed with limited preoxidation, low air flow rate and relative low temperatures at reflood initiation (max T pct = 1870 K). Variables relating to the major signatures (thermal response, hydrogen generation, oxide layer development, oxygen and nitrogen consumption and reflood behaviour) were compared globally and/or at selected locations. In each simulation, the same input models and assumptions are used for both experiments, differing only in respect of the boundary conditions. However, some slight idealisations were made to the assumed boundary conditions in order to avoid ambiguities in the code-to-code comparisons; in this way, it was possible to focus more easily on the key phenomena and hence make the results of the exercise more transparent. Remarks are made concerning the capability of physical modelling within the codes, description of the experiment facility and test conduct as specified in the code input

Investigation of Countercurrent Helium-Air Flows in Air-ingress Accidents for VHTRs

Energy Technology Data Exchange (ETDEWEB)

Sun, Xiaodong; Christensen, Richard; Oh, Chang

2013-10-03

The primary objective of this research is to develop an extensive experimental database for the air- ingress phenomenon for the validation of computational fluid dynamics (CFD) analyses. This research is intended to be a separate-effects experimental study. However, the project team will perform a careful scaling analysis prior to designing a scaled-down test facility in order to closely tie this research with the real application. As a reference design in this study, the team will use the 600 MWth gas turbine modular helium reactor (GT-MHR) developed by General Atomic. In the test matrix of the experiments, researchers will vary the temperature and pressure of the helium— along with break size, location, shape, and orientation—to simulate deferent scenarios and to identify potential mitigation strategies. Under support of the Department of Energy, a high-temperature helium test facility has been designed and is currently being constructed at Ohio State University, primarily for high- temperature compact heat exchanger testing for the VHTR program. Once the facility is in operation (expected April 2009), this study will utilize high-temperature helium up to 900°C and 3 MPa for loss-of-coolant accident (LOCA) depressurization and air-ingress experiments. The project team will first conduct a scaling study and then design an air-ingress test facility. The major parameter to be measured in the experiments is oxygen (or nitrogen) concentration history at various locations following a LOCA scenario. The team will use two measurement techniques: 1) oxygen (or similar type) sensors employed in the flow field, which will introduce some undesirable intrusiveness, disturbing the flow, and 2) a planar laser-induced fluorescence (PLIF) imaging technique, which has no physical intrusiveness to the flow but requires a transparent window or test section that the laser beam can penetrate. The team will construct two test facilities, one for high-temperature helium tests with

Sensitivity studies of air ingress accidents in modular HTGRs

International Nuclear Information System (INIS)

Ball, Syd; Richards, Matt; Shepelev, Sergey

2008-01-01

Postulated air ingress accidents, while of very low probability in a modular high-temperature gas-cooled reactor (HTGR), are of considerable interest to the plant designer, operator, and regulator because of the possibility that the core could sustain significant damage under some circumstances. Sensitivity analyses are described that cover a wide spectrum of conditions affecting outcomes of the postulated accident sequences, for both prismatic and pebble-bed core designs. The major factors affecting potential core damage are the size and location of primary system leaks, flow path resistances, the core temperature distribution, and the long-term availability of oxygen in the incoming gas from a confinement building. Typically, all the incoming oxygen entering the core area is consumed within the reactor vessel, so it is more a matter of where, not whether, oxidation occurs. An air ingress model with example scenarios and means for mitigating damage are described. Representative designs of modular HTGRs included here are a 400-MW(th) pebble-bed reactor (PBR), and a 600-MW(th) prismatic-core modular reactor (PMR) design such as the gas-turbine modular helium reactor (GT-MHR)

Deuterium ingress at rolled joints in Embalse nuclear power plant

International Nuclear Information System (INIS)

Ramos Nervi, J. E.; Schroeter, F.

2013-01-01

Deuterium ingress model at the Rolled Joint has been extensively used for CANDU Nuclear Power Plants Operators in the Life Management of the Pressure Tubes. The importance of understanding the model is vital to avoid delayed hydride cracking at the Rolled Joint. This work reports the first step on develop the model presented on literature to be used in Argentinean CANDU 6, Embalse Nuclear Power Plant. (author)

Air ingress and graphite burning in HTRs: A survey on analytical examinations performed with the code React/Thermix

International Nuclear Information System (INIS)

Moormann, R.

1995-05-01

Analyses on air ingress in the pebble bed reactors PNP-500, THTR-300, HTR-Modul, AVR-II and AVR process heat plant are outlined; in addition, some results for the VHTR with block type fuel are given. Air ingress requires primary circuit depressurization and large leak(s) to reactor buildings and environment and belongs therefore to highly hypothetical events in the sense of classical safety analysis. One accident class examined is air ingress with forced flow by emergency cooling: For this case, the range of mass flow/air content in cooling gas has been evaluated, in which safe core cool down is possible resp. long term core burning occurs; for highest available emergency cooling flow, a safe cool down of the THTR-300, which has no reactor building, is possible for up to 20 vol-% of air in the cooling gas, wheras low flow allows only for about 5 vol-%. If the amount of available air is restricted to the content of a reactor building, as is examined for the PNP-500, relevant consequences have not to be expected; this remains also true for forced convection flow, if burning of CO, formed by graphite oxidation, within the building is considered. For the second accident class examined, air ingress with natural convection flow by chimney draught as studied for the HTR-Modul and some other concepts, the time span until significant fission product release begins has been determined; in case, that the bottom reflector is hot at accident start (> 600 C) and therefore consumes most of the ingressing oxygen, this time span is at least several hours and leak tightening counter measures may be possible. (orig./HP)

ISOTHERMAL AIR INGRESS VALIDATION EXPERIMENTS AT IDAHO NATIONAL LABORATORY: DESCRIPTION AND SUMMARY OF DATA

International Nuclear Information System (INIS)

Oh, Chang H.; Kim, Eung S.

2010-01-01

Idaho National Laboratory performed air ingress experiments as part of validating computational fluid dynamics code (CFD). An isothermal stratified flow experiment was designed and set to understand stratified flow phenomena in the very high temperature gas cooled reactor (VHTR) and to provide experimental data for validating computer codes. The isothermal experiment focused on three flow characteristics unique in the VHTR air-ingress accident: stratified flow in the horizontal pipe, stratified flow expansion at the pipe and vessel junction, and stratified flow around supporting structures. Brine and sucrose were used as heavy fluids and water was used as light fluids. The density ratios were changed between 0.87 and 0.98. This experiment clearly showed that a stratified flow between heavy and light fluids is generated even for very small density differences. The code was validated by conducting blind CFD simulations and comparing the results to the experimental data. A grid sensitivity study was also performed based on the Richardson extrapolation and the grid convergence index method for modeling confidence. As a result, the calculated current speed showed very good agreement with the experimental data, indicating that the current CFD methods are suitable for predicting density gradient stratified flow phenomena in the air-ingress accident.

Modeling of the consequences of an air ingress in the vessel on the source term calculation in a severe accident

International Nuclear Information System (INIS)

Beuzet, E.

2010-01-01

This work deals with severe accidents in nuclear power plants with an air ingress in the vessel. Air, which is very oxidizing, enhances noticeably ruthenium release, due to a high fuel oxidation. Oxygen affinity is decreasing between zircaloy cladding, fuel and ruthenium which is released from fuel as volatile and radio-toxic oxides. The main objective was to develop models for cladding and fuel oxidation and ruthenium release and implement them in the severe accident code MAAP. For each phenomenon, the literature study contributes to establish numerical models, validated against specific experiments. Cladding oxidation by air leads to a dense zirconia layer and, after cracking, a porous zirconia. Its modelling was validated against QUENCH-10 (KIT) and PARAMETER-SF4 (LUCH) experiments and 'NUREG' oxide mass gain law was selected as the best current compromise. Ruthenium release is modelled as an instantaneous oxide volatilisation at the fuel surface, controlled by fuel oxidation, which is itself based on a surface reaction assumption. These models were validated against a selected set of VERCORS (CEA) experiments. Ruthenium release is well-reproduced, particularly for air and steam atmospheres. To finish, an accidental scenario with air ingress in the vessel was simulated: a first value was given for the time needed to completely release ruthenium still present in core and was compared to the other studies. This simulation underlines the high ruthenium release under air conditions. (author)

Study on air ingress during an early stage of a primary-pipe rupture accident of a high-temperature gas-cooled reactor

International Nuclear Information System (INIS)

Hishida, M.; Takeda, T.

1991-01-01

A primary-pipe rupture accident is one of the design-based accidents of the HTTR. As the first step of our final goal of predicting the multicomponent gas flow in a reactor during the early stages of the accident, the present paper aims at studying experimentally and analytically, the basic features of air ingress and gas transportation by transient molecular diffusion and the transient natural convection of a two-component gas mixture. The present paper comprises two main parts. The first part deals with analytical and experimental studies on N 2 ingress (corresponding to air ingress) and gas transportation by molecular diffusion and the one-dimensional natural convection of an He-N 2 two-component gas mixture in a reverse-U-shaped tube. Analytical and experimental results are discussed on the N 2 mole fraction change with time after the simulated pipe rupture and on the initation time of the natural circulation of pure N 2 . The second part deals with a preliminary simulation test of air ingress during the early stages of the accident. The test is performed with a very simple model of the reactor. The experimental results are discussed on the change in mole fraction of air with time and on the initiation time of the natural circulation of pure air. (orig.)

Scaling and design analyses of a scaled-down, high-temperature test facility for experimental investigation of the initial stages of a VHTR air-ingress accident

International Nuclear Information System (INIS)

Arcilesi, David J.; Ham, Tae Kyu; Kim, In Hun; Sun, Xiaodong; Christensen, Richard N.; Oh, Chang H.

2015-01-01

Highlights: • A 1/8th geometric-scale test facility that models the VHTR hot plenum is proposed. • Geometric scaling analysis is introduced for VHTR to analyze air-ingress accident. • Design calculations are performed to show that accident phenomenology is preserved. • Some analyses include time scale, hydraulic similarity and power scaling analysis. • Test facility has been constructed and shake-down tests are currently being carried out. - Abstract: A critical event in the safety analysis of the very high-temperature gas-cooled reactor (VHTR) is an air-ingress accident. This accident is initiated, in its worst case scenario, by a double-ended guillotine break of the coaxial cross vessel, which leads to a rapid reactor vessel depressurization. In a VHTR, the reactor vessel is located within a reactor cavity that is filled with air during normal operating conditions. Following the vessel depressurization, the dominant mode of ingress of an air–helium mixture into the reactor vessel will either be molecular diffusion or density-driven stratified flow. The mode of ingress is hypothesized to depend largely on the break conditions of the cross vessel. Since the time scales of these two ingress phenomena differ by orders of magnitude, it is imperative to understand under which conditions each of these mechanisms will dominate in the air ingress process. Computer models have been developed to analyze this type of accident scenario. There are, however, limited experimental data available to understand the phenomenology of the air-ingress accident and to validate these models. Therefore, there is a need to design and construct a scaled-down experimental test facility to simulate the air-ingress accident scenarios and to collect experimental data. The current paper focuses on the analyses performed for the design and operation of a 1/8th geometric scale (by height and diameter), high-temperature test facility. A geometric scaling analysis for the VHTR, a time

Separate-effect tests on zirconium cladding degradation in air ingress situations

Energy Technology Data Exchange (ETDEWEB)

Duriez, C. [Institut de Radioprotection et de Surete Nucleaire, IRSN, Direction de Prevention des Accidents Majeurs, Centre de Cadarache, 13115 St Paul Lez Durance (France)], E-mail: christian.duriez@irsn.fr; Steinbrueck, M. [Forschungszentrum Karlsruhe, FZK, Institut fuer Materialforschung, Postfach 3640, 76021 Karlsruhe (Germany); Ohai, D.; Meleg, T. [Institute for Nuclear Research, INR, Nuclear Material and Corrosion Department, Pitesti, 115400 Mioveni Arges (Romania); Birchley, J.; Haste, T. [Paul Scherrer Institute, 5232 Villigen PSI (Switzerland)

2009-02-15

In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air + steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK, IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the 'as-received' state, or after pre-oxidation in steam. 'Analytical' tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 deg. C up to 1500 deg. C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of

Separate-effect tests on zirconium cladding degradation in air ingress situations

International Nuclear Information System (INIS)

Duriez, C.; Steinbrueck, M.; Ohai, D.; Meleg, T.; Birchley, J.; Haste, T.

2009-01-01

In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air + steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK, IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the 'as-received' state, or after pre-oxidation in steam. 'Analytical' tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 deg. C up to 1500 deg. C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale

Autonomous Landing and Ingress of Micro-Air-Vehicles in Urban Environments Based on Monocular Vision

Science.gov (United States)

Brockers, Roland; Bouffard, Patrick; Ma, Jeremy; Matthies, Larry; Tomlin, Claire

2011-01-01

Unmanned micro air vehicles (MAVs) will play an important role in future reconnaissance and search and rescue applications. In order to conduct persistent surveillance and to conserve energy, MAVs need the ability to land, and they need the ability to enter (ingress) buildings and other structures to conduct reconnaissance. To be safe and practical under a wide range of environmental conditions, landing and ingress maneuvers must be autonomous, using real-time, onboard sensor feedback. To address these key behaviors, we present a novel method for vision-based autonomous MAV landing and ingress using a single camera for two urban scenarios: landing on an elevated surface, representative of a rooftop, and ingress through a rectangular opening, representative of a door or window. Real-world scenarios will not include special navigation markers, so we rely on tracking arbitrary scene features; however, we do currently exploit planarity of the scene. Our vision system uses a planar homography decomposition to detect navigation targets and to produce approach waypoints as inputs to the vehicle control algorithm. Scene perception, planning, and control run onboard in real-time; at present we obtain aircraft position knowledge from an external motion capture system, but we expect to replace this in the near future with a fully self-contained, onboard, vision-aided state estimation algorithm. We demonstrate autonomous vision-based landing and ingress target detection with two different quadrotor MAV platforms. To our knowledge, this is the first demonstration of onboard, vision-based autonomous landing and ingress algorithms that do not use special purpose scene markers to identify the destination.

Oxidation kinetics of innovative carbon materials with respect to severe air ingress accidents in HTRs and graphite disposal or processing

International Nuclear Information System (INIS)

Schloegel, Baerbel

2010-01-01

Currently future nuclear reactor concepts of the Fourth Generation (Gen IV) are under development. To some extend they apply with new, innovative materials developed just for this purpose. This thesis work aims at a concept of Generation IV Very High Temperature Reactors (VHTR) in the framework of the European project RAPHAEL (ReActor for Process heat, Hydrogen And ELectricity generation). The concept named ANTARES (AREVA New Technology based on advanced gas-cooled Reactors for Energy Supply) was developed by AEVA NP. It is a helium cooled, graphite moderated modular reactor for electricity and hydrogen production, by providing the necessary process heat due to its high working temperature. Particular attention is given here to oxidation kinetics of newly developed carbon materials (NBG-17) with still unknown but needed information in context of severe air ingress accident in VHTR's. Special interest is paid to the Boudouard reaction, the oxidation of carbon by CO 2 . In case of an air ingress accident, carbon dioxide is produced in the primary reaction of atmospheric oxygen with reflector graphite. From there CO 2 could flow into the reactor core causing further damage by conversion into CO. The purpose of this thesis is to ascertain if and to what degree this could happen. First of all oxidation kinetic data of the Boudouard reaction with NBG-17 is determined by experiments in a thermo gravimetric facility. The measurements are evaluated and converted into a common formula and a Langmuir-Hinshelwood similar oxidation kinetic equation, as input for the computer code REACT/THERMIX. This code is then applied to analyse severe air ingress accidents for several air flow rates. The results are discussed for two accident situations, in which a certain graphite burn off is achieved. All cases show much more damage to the graphite bottom reflector than to the reactor core. Thus the bottom reflector will lose its structural integrity much earlier than the core itself will

Computational fluid dynamics analysis of the initial stages of a VHTR air-ingress accident using a scaled-down model

Energy Technology Data Exchange (ETDEWEB)

Ham, Tae K., E-mail: taekyu8@gmail.com [Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210 (United States); Arcilesi, David J., E-mail: arcilesi.1@osu.edu [Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210 (United States); Kim, In H., E-mail: ihkim0730@gmail.com [Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210 (United States); Sun, Xiaodong, E-mail: sun.200@osu.edu [Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210 (United States); Christensen, Richard N., E-mail: rchristensen@uidaho.edu [Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210 (United States); Oh, Chang H. [Idaho National Laboratory, Idaho Falls, ID 83402 (United States); Kim, Eung S., E-mail: kes7741@snu.ac.kr [Idaho National Laboratory, Idaho Falls, ID 83402 (United States)

2016-04-15

Highlights: • Uncertainty quantification and benchmark study are performed to validate an ANSYS FLUENT computer model for a depressurization process in a high-temperature gas-cooled reactor. • An ANSYS FLUENT computer model of a 1/8th scaled-down geometry of a VHTR hot exit plenum is presented, which is similar to the experimental test facility that has been constructed at The Ohio State University. • Using the computer model of the scaled-down geometry, the effects of the depressurization process and flow oscillations on the subsequent density-driven stratified flow phenomenology are examined computationally. • The effects of the scaled-down hot exit plenum internal structure temperature on the density-driven stratified flow phenomenology are investigated numerically. - Abstract: An air-ingress accident is considered to be one of the design basis accidents of a very high-temperature gas-cooled reactor (VHTR). The air-ingress accident is initiated, in its worst-case scenario, by a complete break of the hot duct in what is referred to as a double-ended guillotine break. This leads to an initial loss of the primary helium coolant via depressurization. Following the depressurization process, the air–helium mixture in the reactor cavity could enter the reactor core via the hot duct and hot exit plenum. In the event that air ingresses into the reactor vessel, the high-temperature graphite structures in the reactor core and hot plenum will chemically react with the air, which could lead to damage of in-core graphite structures and fuel, release of carbon monoxide and carbon dioxide, core heat up, failure of the structural integrity of the system, and eventually the release of radionuclides to the environment. Studies in the available literature focus on the phenomena of the air ingress accident that occur after the termination of the depressurization, such as density-driven stratified flow, molecular diffusion, and natural circulation. However, a recent study

Experimental study on air ingress during a primary pipe rupture accident with a graphite reactor core simulator

International Nuclear Information System (INIS)

Takeda, Tetsuaki; Hishida, Makoto; Baba, Shinichi

1991-11-01

When a primary coolant pipe of a High Temperature Gas Cooled Reactor (HTGR) ruptures, helium gas in the reactor core blows out into the container, and the primary cooling system reduces the pressure. After the pressures are balanced between the reactor and the container, air is expected to enter into the reactor core from the breach. It seems to be probable that the graphite structures is oxidized by air. Hence, it is necessary to investigate the air ingress process and the behavior of the generating gases by the oxidation reactions. The previous experimental study is performed on the molecular diffusion and natural convection of the two component gas mixtures using a test model simulating simply the reactor. Objective of the study was to investigate the air ingress process during the early stage of the primary pipe rupture accident. However, since the model did not have any kind of graphite components, the reaction between graphite and oxygen was not simulated. The present model includes the reactor core and the high temperature plenum simulators made of graphite. The major results obtained in the present study are summarized in the followings: (1) The air ingress process with graphite oxidation reaction is similar to that without the reaction qualitatively. (2) When the reactor core simulator is maintained at low temperatures (lower than 450degC), the initiation time of the natural circulation of air is almost equal to that of the natural circulation of nitrogen. On the other hand, when the temperature of the reactor core simulator is high (more than 500degC), the initiation time of the natural circulation of air is earlier than that of nitrogen. (3) When the temperature of the reactor core simulator is higher than 600degC, oxygen is almost dissipated by the graphite structures. When the temperature of the reactor core simulator is below 700degC, carbon dioxide mainly is generated by the oxidation reactions. (author)

Safety analysis results for cryostat ingress accidents in ITER

International Nuclear Information System (INIS)

Merrill, B.J.; Cadwallader, L.C.; Petti, D.A.

1996-01-01

Accidents involving the ingress of air or water into the cryostat of the International Thermonuclear Experimental Reactor (ITER) tokamak design have been analyzed with a modified version of the MELCOR code for the ITER Non-site Specific Safety Report (NSSR-1). The air ingress accident is the result of a postulated breach of the cryostat boundary into an adjoining room. MELCOR results for this accident demonstrate that the condensed air mass and increased heat loads are not a magnet safety concern, but that the partial vacuum in the adjoining room must be accommodated in the building design. The water ingress accident is the result of a postulated magnet arc that results in melting of a Primary Heat Transport System (PHTS) coolant pipe, discharging PHTS water and PHTS water activated corrosion products and HTO into the cryostat. MELCOR results for this accident demonstrate that the condensed water mass and increased heat loads are not a magnet safety concern, that the cryostat pressure remains below design limits, and that the corrosion product and HTO releases are well within the ITER release limits

Study air ingress into the reactor vessel using ICARE/CATHARE V2.0 in case of severe accident

International Nuclear Information System (INIS)

Gwenaelle Le Dantec; Fichot, F.

2005-01-01

Full text of publication follows: Safety analyses show that core degradation during a severe reactor accident would not be uniform. This was confirmed by TMI2 examinations. In fact, a central region of the core may overheat, melt and flow down to the lower plenum of the reactor while peripheral regions of the core would remain almost intact. Following rupture of the vessel by molten debris, air may be drawn from the containment by natural convection into the reactor coolant system, and react with the intact rods. Studying air ingress into the reactor vessel is of interest because the interaction of air with Zircaloy cladding can strongly affect the evolution of severe accident scenarios. The main effects are heat generation, increasing clad degradation, fission product release and nitriding. In case of air/steam recirculation in the vessel, significant nitriding of cladding can occur. The resulting ZrN phase is characterized by its brittleness and instability under oxidizing conditions, Oxidation of pre-existing ZrN phase layers has been observed to result in violent oxidation and heat release. Therefore, the first consequence for safety is a risk of strong deflagration in the vessel if a large number of rods on which a substantial layer of ZrN has grown are suddenly in contact with oxygen or steam. The second consequence is a late melting of core materials due to the very exothermic oxidation, leading to a late release of materials out of the reactor pressure vessel (RPV). In this paper we present an ICARE/CATHARE V2.0 calculation simulating air ingress into the vessel and in particular to describe the nitriding due to natural convection in the reactor vessel. The basic modeling and the necessary extensions of both ICARE and CATHARE are explained. The natural circulation is calculated to predict the regions of oxygen starvation where nitriding takes place. Key words: air ingress, nitriding, ICARE/CATHARE V2.0. (authors)

ANALISIS EFEK KECELAKAAN WATER INGRESS TERHADAP REAKTIVITAS DOPPLER TERAS RGTT200K

Directory of Open Access Journals (Sweden)

Zuhair Zuhair

2015-03-01

Full Text Available Dalam high temperature reactor, koefisien reaktivitas temperatur yang didesain negatif menjamin reaksi fisi dalam teras tetap berada di bawah kendali dan panas peluruhan tidak akan pernah melelehkan bahan bakar yang menyebabkan terlepasnya zat radioaktif ke lingkungan. Namun masuknya air (water ingress ke dalam teras reaktor akibat pecahnya tabung penukar panas generator uap, yang dikenal sebagai salah satu kecelakaan dasar desain, dapat mengintroduksi reaktivitas positif dengan potensi bahaya lainnya seperti korosi grafit dan kerusakan material struktur reflektor. Makalah ini akan menganalisis efek kecelakaan water ingress terhadap reaktivitas Doppler teras RGTT200K. Kapabilitas koefisien reaktivitas Doppler untuk mengkompensasi reaktivitas positif yang timbul selama kecelakaan water ingress akan diuji melalui serangkaian perhitungan dengan program MCNPX dan pustaka ENDF/B-VII untuk perubahan temperatur bahan bakar dari 800K hingga 1800K. Tiga opsi kernel bahan bakar UO2, ThO2/UO2 dan PuO2 dengan tiga model kisi bahan bakar pebble di teras reaktor diterapkan untuk kondisi water ingress dengan densitas air dari 0 hingga 1.000 kg/m3. Hasil perhitungan memperlihatkan koefisien reaktivitas Doppler tetap negatif untuk seluruh opsi bahan bakar yang dipertimbangkan bahkan untuk posibilitas water ingress yang besar. Efek water ingress lebih kuat pada model kisi dengan fraksi packing lebih rendah karena lebih banyak volume yang tersedia untuk air yang memasuki teras reaktor. Efek water ingress juga lebih kuat di teras uranium dibandingkan teras thorium dan plutonium sebagai konsekuensi dari fenomena Doppler dimana absorpsi neutron di daerah resonansi 238U lebih besar daripada 232Th dan 240Pu. Secara keseluruhan dapat disimpulkan bahwa, koefisien Doppler teras RGTT200K mampu mengkompensasi insersi reaktivitas yang diintroduksi oleh kecelakaan water ingress. Teras RGTT200K dengan bahan bakar UO2, ThO2/UO2 dan PuO2 dapat mempertahankan fitur keselamatan

Effect of air ingress on the energy performance of coal fired thermal power plants

International Nuclear Information System (INIS)

Siddhartha Bhatt, M.

2007-01-01

Ingress of air in boilers leads to drops in energy efficiency. This paper presents the effects of air ingress in the combustion zone, post-combustion zone and air pre-heater (APH) on the energy efficiency and loading capacity of a coal fired thermal power plant operating on fuel with high ash (35-45%). The optimal O 2 in the flue gas for a pulverized coal fired system is 3.5% (corresponding to 20% excess air). The operating values are in the range of 4.2-6.0% in membrane type boilers and up to 10% in refractory type boilers (after sustained periods of operation). The leakage rate of boilers (up to the entrance of the APH) is designed at 0.2% while the average operating values are 7.25% for membrane type enclosures and 33.61% for refractory enclosures. The leakage rate of the APH is designed at 5.0% while the operating values range from 13.66% to 20.13% for rotary and tubular APHs. When the O 2 in the combustion zone varies from 3.5% to 8.0%, efficiency drops of 2.0% points are experienced in the boiler and turbine separately, and the gross overall efficiency drop is ∼3.0% points. The units do not experience any capacity drop up to an O 2 in the flue gas of 6.0% before the APH. At an O 2 in the flue gas (before APH) of 7.2%, a mild limitation on the unit capacity of around 2-3% is experienced. When O 2 in the flue gas (before APH) reaches a level of 9.0%, 20% capacity drop of the unit is experienced due to which the plant load cannot be raised higher than 80%. Beyond the level of 9.0% (rare occurrence), the unit is quite difficult to operate and has to be taken off for overhaul

The effects of applying silicon carbide coating on core reactivity of pebble-bed HTR in water ingress accident

Energy Technology Data Exchange (ETDEWEB)

Zuhair, S.; Setiadipura, Topan [National Nuclear Energy Agency of Indonesia, Serpong Tagerang Selatan (Indonesia). Center for Nuclear Reactor Technology and Safety; Su' ud, Zaki [Bandung Institute of Technology (Indonesia). Dept. of Physics

2017-03-15

Graphite is used as the moderator, fuel barrier material, and core structure in High Temperature Reactors (HTRs). However, despite its good thermal and mechanical properties below the radiation and high temperatures, it cannot avoid corrosion as a consequence of an accident of water/air ingress. Degradation of graphite as a main HTR material and the formation of dangerous CO gas is a serious problem in HTR safety. One of the several steps that can be adopted to avoid or prevent the corrosion of graphite by the water/air ingress is the application of a thin layer of silicon carbide (SiC) on the surface of the fuel element. This study investigates the effect of applying SiC coating on the fuel surfaces of pebble-bed HTR in water ingress accident from the reactivity points of view. A series of reactivity calculations were done with the Monte Carlo transport code MCNPX and continuous energy nuclear data library ENDF/B-VII at temperature of 1200 K. Three options of UO{sub 2}, PuO{sub 2}, and ThO{sub 2}/UO{sub 2} fuel kernel were considered to obtain the inter comparison of the core reactivity of pebble-bed HTR in conditions of water/air ingress accident. The calculation results indicated that the UO{sub 2}-fueled pebble-bed HTR reactivity was slightly reduced and relatively more decreased when the thickness of the SiC coating increased. The reactivity characteristic of ThO{sub 2}/UO{sub 2}-fueled pebble-bed HTR showed a similar trend to that of UO{sub 2}, but did not show reactivity peak caused by water ingress. In contrast with UO{sub 2}- and ThO{sub 2}-fueled pebble-bed HTR, although the reactivity of PuO{sub 2}-fueled pebble-bed HTR was the lowest, its characteristics showed a very high reactivity peak (0.33 Δk/k) and this introduction of positive reactivity is difficult to control. SiC coating on the surface of the plutonium fuel pebble has no significant impact. From the comparison between reactivity characteristics of uranium, thorium and plutonium cores with 0

Analysis of diffusion process and influence factors in the air ingress accident of the HTR-PM

Energy Technology Data Exchange (ETDEWEB)

Yanhua, Zheng, E-mail: zhengyh@mail.tsinghua.edu.cn; Fubing, Chen; Lei, Shi

2014-05-01

Air ingress, one of the beyond design basis accidents for high temperature gas-cooled reactors, receives high attention during the design of the 250 MW pebble-bed modular high temperature gas-cooled reactor (HTR-PM), because it may result in severe consequence including the corrosion of the fuel element and graphite reflector. The diffusion process and the set-up time of the stable natural convection after the double-ended guillotine break of the hot-gas duct are studied in the paper. On the basis of the preliminary design of the HTR-PM and its DLOCA analysis results, the diffusion process, as well as the influence of the core temperature distribution and the length of the hot-gas duct, is studied with the DIFFLOW code, which adopts a one-dimension variable cross-section diffusion model with fixed wall temperature. To preliminarily estimate the influence of chemical reaction between oxygen and graphite, which will change the gas component of the mixture, the diffusion processes between the He/N{sub 2}, He/O{sub 2}, He/CO and He/CO{sub 2} are calculated, respectively. Furthermore, the code has been improved and the varying wall temperature can be simulated. The more accurate analysis is carried out with the changing temperature distribution from the DLOCA calculation. The analysis shows that there is enough time to adopt appropriate mitigation measures to stop the air ingress and the severe consequence of fuel element damage and large release of fission product can be avoided.

Plating end fittings to reduce hydrogen ingress at rolled joints in CANDU reactors

International Nuclear Information System (INIS)

White, A.J.; Urbanic, V.F.; Bahurmuz, A.A.; Clendening, W.R.; Joynes, R.; McDougall, G.M.; Skinner, B.C.; Venkatapathi, S.

1993-10-01

Zr-2.5Nb pressure tubes in CANDU nuclear reactors absorb hydrogen at a low rate from the primary heat transport water circulated through the tubes. Extra hydrogen is picked up at the rolled joints that connect the pressure tubes to out-of-core steel piping. This enhanced ingress may contribute to pressure-tube cracking at incorrectly assembled joints. The risk of pressure-tube failure has been decreased by ensuring correct joint assembly, and could be further decreased by reducing hydrogen ingress at rolled joints. This paper reviews progress toward using plated end fittings to reduce rolled-joint hydrogen ingress

Ruthenium transport experiments in air ingress accident conditions

Energy Technology Data Exchange (ETDEWEB)

Teemu, Karkele; Ulrika, Backman; Ari, Auvinen; Unto, Tapper; Jorma, Jokiniemi [VTT Technical Research Centre of Finland, Fine Particles (Finland); Riitta, Zilliacus; Maija, Lipponen; Tommi, Kekki [VTT Technical Research Centre of Finland, Accident Management (Finland); Jorma, Jokiniemi [Kuopio Univ., Dept. of Environmental Sciences, Fine Particle and Aerosol Technology Lab. (Finland)

2007-07-01

In this study the release, transport and speciation of ruthenium in conditions simulating an air ingress accident was studied. Ruthenium dioxide was exposed to oxidising environment at high temperature (1100-1700 K) in a tubular flow furnace. At these conditions volatile ruthenium species were formed. A large fraction of the released ruthenium was deposited in the tube as RuO{sub 2}. Depending on the experimental conditions 1-26 wt% of the released ruthenium was trapped in the outlet filter as RuO{sub 2} particles. In stainless steel tube 0-8.8 wt% of the released ruthenium reached the trapping bottle as gaseous RuO{sub 4}. A few experiments were carried out, in which revaporization of ruthenium deposited on the tube walls was studied. In these experiments, oxidation of RuO{sub 2} took place at a lower temperature. During revaporization experiments 35-65 % of ruthenium was transported as gaseous RuO{sub 4}. In order to close mass balance and achieve better time resolution 4 experiments were carried out using a radioactive tracer. In these experiments ruthenium profiles were measured. These experiments showed that the most important retention mechanism was decomposition of gaseous RuO{sub 3} into RuO{sub 2} as the temperature of the furnace was decreasing. In these experiments the transport rate of gaseous ruthenium was decreasing while the release rate was constant.

Response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. Proceedings of a technical committee meeting held in Beijing, China, 25-27 October 1993

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

The meeting was convened by the IAEA on the recommendation of the IAEA`s International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Netherlands, Switzerland, the Russian Federation, the United Kingdom and the United States of America. The meeting covered the following topics: experimental investigations of the effects of air and water ingress; predicted response of fuel, graphite and other reactor components; options for minimizing or mitigating the effects of air or water ingress. 19 papers were presented at the meeting. A separate abstract was prepared for each of these papers. Refs, figs and tabs.

Oxidation kinetics of innovative carbon materials with respect to severe air ingress accidents in HTRs and graphite disposal or processing; Oxidationskinetik innovativer Kohlenstoffmaterialien hinsichtlich schwerer Lufteinbruchstoerfaelle in HTR's und Graphitentsorgung oder Aufbereitung

Energy Technology Data Exchange (ETDEWEB)

Schloegel, Baerbel

2010-07-01

Currently future nuclear reactor concepts of the Fourth Generation (Gen IV) are under development. To some extend they apply with new, innovative materials developed just for this purpose. This thesis work aims at a concept of Generation IV Very High Temperature Reactors (VHTR) in the framework of the European project RAPHAEL (ReActor for Process heat, Hydrogen And ELectricity generation). The concept named ANTARES (AREVA New Technology based on advanced gas-cooled Reactors for Energy Supply) was developed by AEVA NP. It is a helium cooled, graphite moderated modular reactor for electricity and hydrogen production, by providing the necessary process heat due to its high working temperature. Particular attention is given here to oxidation kinetics of newly developed carbon materials (NBG-17) with still unknown but needed information in context of severe air ingress accident in VHTR's. Special interest is paid to the Boudouard reaction, the oxidation of carbon by CO{sub 2}. In case of an air ingress accident, carbon dioxide is produced in the primary reaction of atmospheric oxygen with reflector graphite. From there CO{sub 2} could flow into the reactor core causing further damage by conversion into CO. The purpose of this thesis is to ascertain if and to what degree this could happen. First of all oxidation kinetic data of the Boudouard reaction with NBG-17 is determined by experiments in a thermo gravimetric facility. The measurements are evaluated and converted into a common formula and a Langmuir-Hinshelwood similar oxidation kinetic equation, as input for the computer code REACT/THERMIX. This code is then applied to analyse severe air ingress accidents for several air flow rates. The results are discussed for two accident situations, in which a certain graphite burn off is achieved. All cases show much more damage to the graphite bottom reflector than to the reactor core. Thus the bottom reflector will lose its structural integrity much earlier than the

Googles Augmented-Reality-Game "Ingress"

Directory of Open Access Journals (Sweden)

Karl H. Stingeder

2013-12-01

Full Text Available Das an das "Geocoaching"-Spielprinzip erinnernde Augmented-­Reality-Game "Ingress" ist auf allen mit Android-Betriebssystem ausgestatteten Smartphones spielbar. Das Alleinstellungsmerkmal des Spiels ist gleich­zeitig auch das beste Patent-Rezept für bzw. gegen notorisches "Couch-Potato-ing": Das Game-Design des "Draußenspiels" erfordert jedoch stets die physische Anwesenheit der SpielerInnen am realen Ort des Geschehens, meist touristisch attraktive Sehenswürdigkeiten und architektonisch markante Plätze. Sobald "Ingress" per App am Smart­phone gestartet wird, stehen Interaktionen und Machtverhältnisse auf dem Handy-Display im Dreh- und Angelpunkt des Geschehens. Die Spielgrafik ist auf das Wesentliche reduziert und erinnert an die Optik von Videospielen der 80er Jahre. "Ingress" im Allgemeinen sowie "Magnus13", die erste von Google organisierte Fan-Veranstaltung Österreichs mit mehreren Hundert TeilnehmerInnen und ist mit einer "digitalen Schnitzeljagd" vergleichbar: Gemeinsam ist der klassischen "Schnitzeljagd" und dem digitalen "Schere-Schein-Papier" Prinzip von "Ingress" die tragende Rolle des im Spiel entstehenden Gemeinschaftsgefühls, welche in einer hohen Langzeitmotivation mündet. Trotz aller Euphorie, ob des unkonventionellen Augmented-Reality-Spielkonzepts und des in Folge der sozialen Dynamik außergewöhnlichen Sucht­potentials, ist angesichts von Edward Snowden und vielfältiger NSA-Abhörmaßnahmen, eine gesunde Portion Skepsis angebracht: Welchen Zweck erfüllt "Ingress"? Gibt es ein verhülltes "Mittel zum Zweck"? Welche Gefahren bestehen mit einer systematischen Auswertung des umfangreichen, ortsrelevanten Daten-Sammelsuriums? "Ingress" verdeutlicht trotz aller Risiken den soziokulturellen Bedeutungswandel des digitalen Spiels: Spiele per se und das Spiel als soziale Interaktion sind aktuell dabei, alle Bereiche unseres Lebens zu erfassen.

Experimental and analytical investigations to air and steam ingress into the vacuum vessel of fusion reactors

International Nuclear Information System (INIS)

Kruessenberg, A.K.

1996-12-01

The basic fusion safety objective is the development of fusion power plants with features that protect individuals, society and the environment by establishing and maintaining an effective defence against radiological and other hazards. The most important specific principle is the establishment of three sequential levels of defence, characterized in priority order by prevention, protection and mitigation. The safety conscious selection of materials as one prevention feature gives the basis for the work described in this report. In order to protect the metallic first wall of fusion reactors from direct interaction with the plasma an extra armour is foreseen. Carbon offers the features low atomic number, high melting point, high thermal conductivity and good mechanical stability up to high temperatures making it to a favourite armour material. Looking on the safety behaviour of fusion reactors it has to be noted that carbon is unstable against oxidizing media like oxygen and steam at high temperatures und carbon has a high sorption capacity for radiologically important tritium. And tritium used as intermediate fuel in the actual reactor concepts is the one form radioactivity is present in fusion reactors. Accidents like loss of vacuum (LOVA) will lead to an air ingress into the vacuum vessel, oxidation of the hot carbon and a partial mobilization of the sorbed tritium. In a similar manner loss of coolant into vacuum (LOCIV) will lead to a water/steam ingress into the vacuum vessel, also accompanied by carbon oxidation and tritium release. (orig.)

Oxygen ingress : a practical look at typical ingress mechanisms and the consequences

Energy Technology Data Exchange (ETDEWEB)

Lerbscher, J. [Baker Hughes Canada, Calgary, AB (Canada); Marlowe, D. [ChevronTexaco, Kenai, AK (United States); Thomas, J. [Baker Hughes, Edmonton, AB (Canada)

2008-07-01

This paper discussed methods of identifying and treating oxygen corrosion in hydrocarbon processing facilities. Oxygen corrosion is often misdiagnosed during the course of corrosion failure analyses. Measures to find the source of ingress are only typically initiated when test results demonstrate significant sources of oxygen within processing systems. The iron oxides produced as byproducts from oxygen reactions increase pitting and corrosion rates, and most of the chemical inhibitors used in oil and gas processing are not designed to work in the presence of oxygen. Oxygen reacts with hydrogen sulfide (H{sub 2}S) to form elemental sulfur. The high pressures used in processing facilities enhance the thermodynamic and kinetic tendencies of the chemical reactions with oxygen. Sulfur particles are known to enhance corrosion rates by an order of magnitude, and can also cause fouling and flow restrictions. Oxygen ingress can occur via vapor recovery unit, vacuum excursions, and liquid storage tanks. Symptoms that indicate oxygen ingress can include the presence of iron compounds in solid samples; the presence of sulfur; fouling of wet gas transmission lines; the presence of ionic polysulfides in the aqueous phase; higher corrosion rates than predicted; and the degradation of glycols in dehydration units. Portable gas chromatography, oxygen detection vials, and X-ray diffraction analysis techniques are used to detect oxygen ingress. Real time oxygen monitors are also connected to SCADA systems. It was concluded that oxygen testing should be conducted periodically in order to identify and eliminate its source of entry. A technical summary of corrosive species was included. 1 tab., 15 figs.

Pulmonic Ingressive Speech in Shetland English

Science.gov (United States)

Sundkvist, Peter

2012-01-01

This paper presents a study of pulmonic ingressive speech, a severely understudied phenomenon within varieties of English. While ingressive speech has been reported for several parts of the British Isles, New England, and eastern Canada, thus far Newfoundland appears to be the only locality where researchers have managed to provide substantial…

Modeling moisture ingress through simplified concrete crack geometries

DEFF Research Database (Denmark)

Pease, Bradley Justin; Michel, Alexander; Geiker, Mette Rica

2011-01-01

, considered to have two parts; 1) a coalesced crack length which behaves as a free-surface for moisture ingress, and 2) an isolated microcracking length which resists ingress similarly to the bulk material. Transport model results are compared to experimental results from steel fibre reinforced concrete wedge......This paper introduces a numerical model for ingress in cracked steel fibre reinforced concrete. Details of a simplified crack are preset in the model’s geometry using the cracked hinge model (CHM). The total crack length estimated using the CHM was, based on earlier work on conventional concrete...... on moisture ingress. Results from the transport model indicate the length of the isolated microcracks was approximately 19 mm for the investigated concrete composition....

Assessments of Water Ingress Accidents in a Modular High-Temperature Gas-Cooled Reactor

International Nuclear Information System (INIS)

Zhang Zuoyi; Dong Yujie; Scherer, Winfried

2005-01-01

Severe water ingress accidents in the 200-MW HTR-module were assessed to determine the safety margins of modular pebble-bed high-temperature gas-cooled reactors (HTR-module). The 200-MW HTR-module was designed by Siemens under the criteria that no active safety protection systems were necessary because of its inherent safe nature. For simulating the behavior of the HTR-module during severe water ingress accidents, a water, steam, and helium multiphase cavity model was developed and implemented in the dynamic simulator for nuclear power plants (DSNP) simulation system. Comparisons of the DSNP simulations incorporating these models with experiments and with calculations using the time-dependent neutronics and temperature dynamics code were made to validate the simulation. The analysis of the primary circuit showed that the maximum water concentration increase in the reactor core was 3 s). The water vaporization in the steam generator and characteristics of water transport from the steam generator to the reactor core would reduce the rate of water ingress into the reactor core. The analysis of a full cavitation of the feedwater pump showed that if the secondary circuit could be depressurized, the feedwater pump would be stopped by the full cavitation. This limits the water transported from the deaerator to the steam generator. A comprehensive simulation of the HTR-module power plant showed that the water inventory in the primary circuit was limited to ∼3000 kg. The nuclear reactivity increase caused by the water ingress would lead to a fast power excursion, which would be inherently counterbalanced by negative feedback effects. The integrity of the fuel elements, because the safety-relevant temperature limit of 1600 deg. C is not reached in any case, is not challenged

Chloride ingress in cement paste and mortar

DEFF Research Database (Denmark)

Jensen, Ole Mejlhede; Hansen, Per Freiesleben; Coats, Alison M.

1999-01-01

In this paper chloride ingress in cement paste and mortar is followed by electron probe microanalysis. The influence of several paste and exposure parameters on chloride ingress are examined (e.g., water-cement ratio, silica fume addition, exposure time, and temperature), The measurements...

Containment Performance Evaluation of a Sodium Fire Event Due to Air Ingress into the Cover Gas Region of the Reactor Vessel in the PGSFR

International Nuclear Information System (INIS)

Ahn, Sang June; Chang, Won-Pyo; Kang, Seok Hun; Choi, Chi-Woong; Yoo, Jin; Lee, Kwi Lim; Jeong, Jae-Ho; Lee, Seung Won; Jeong, Taekyeong; Ha, Kwi-Seok

2015-01-01

Comparing with the light water reactor, sodium as a reactor coolant violently reacts with oxygen in the containment atmosphere. Due to this chemical reaction, heat generated from the combustion heat increases the temperature and pressure in the containment atmosphere. The structural integrity of the containment building which is a final radiological defense barrier is threaten. A sodium fire event in the containment due to air ingress into the cover gas region in the reactor vessel is classified as one of the design basis events in the PGSFR. This event comes from a leak or crack on the reactor upper closure header surface. It accompanys an event of the radiological fission products release to the inside the containment. In this paper, evaluation for the sodium fire and radiological influence due to air ingress into the cover gas region of the reactor vessel is described. To evaluate this event, the CONTAIN-LMR, MACCS-II and OR-IGEN-II codes are used. For the sodium pool fire event in the containment, the performance evaluation and radiological influence are carried out. In the thermal hydraulic aspects, the 1 cell containment yields the most conservative result. In this event, the maximum temperature and pressure in the containment are calculated 0.185 MPa, 280.0 .deg. C, respectively. The radiological dose at the EAB and LPZ are below the acceptance criteria specified in the 10CFR100

Containment Performance Evaluation of a Sodium Fire Event Due to Air Ingress into the Cover Gas Region of the Reactor Vessel in the PGSFR

Energy Technology Data Exchange (ETDEWEB)

Ahn, Sang June; Chang, Won-Pyo; Kang, Seok Hun; Choi, Chi-Woong; Yoo, Jin; Lee, Kwi Lim; Jeong, Jae-Ho; Lee, Seung Won; Jeong, Taekyeong; Ha, Kwi-Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Comparing with the light water reactor, sodium as a reactor coolant violently reacts with oxygen in the containment atmosphere. Due to this chemical reaction, heat generated from the combustion heat increases the temperature and pressure in the containment atmosphere. The structural integrity of the containment building which is a final radiological defense barrier is threaten. A sodium fire event in the containment due to air ingress into the cover gas region in the reactor vessel is classified as one of the design basis events in the PGSFR. This event comes from a leak or crack on the reactor upper closure header surface. It accompanys an event of the radiological fission products release to the inside the containment. In this paper, evaluation for the sodium fire and radiological influence due to air ingress into the cover gas region of the reactor vessel is described. To evaluate this event, the CONTAIN-LMR, MACCS-II and OR-IGEN-II codes are used. For the sodium pool fire event in the containment, the performance evaluation and radiological influence are carried out. In the thermal hydraulic aspects, the 1 cell containment yields the most conservative result. In this event, the maximum temperature and pressure in the containment are calculated 0.185 MPa, 280.0 .deg. C, respectively. The radiological dose at the EAB and LPZ are below the acceptance criteria specified in the 10CFR100.

Discussion on amount of water ingress mass in steam generator heat-exchange tube rupture accident of high- temperature gas-cooled reactor

International Nuclear Information System (INIS)

Wang Yan; Zheng Yanhua; Shi Lei; Li Fu; Sun Ximing

2009-01-01

The steam generator heat-exchange tube rupture (SGTR) accident which will result in the water ingress to the primary circuit of reactor is an important and particular accident for high-temperature gas-cooled reactor (HTGR). The analysis of the water ingress accident is significant for verifying the inherent safety characteristics of HTGR. The amount of water ingress mass is one of the decisive factors for the seriousness of the accident consequence. The 250 MW Pebble-bed Modular High-Temperature Gas-cooled Reactor (HTR-PM) designed by Institute of Nuclear and New Energy Technology of Tsinghua University was selected as an example of analysis. The analysis results show that the amount of water ingress mass is not only affected directly with the broken position and the broken area of the tubes, but also related with the diameter of draining piping and restrictor, draining control valve, action setting of emptier system. With reasonable parameters chosen, the water in steam generator could be drained effectively, so it will prevent the primary circuit of reactor from water ingress in large quantity and reduce the radioactive isotopes ingress to the secondary circuit. (authors)

Chloride Ingress in Concrete Cracks under Cyclic Loading

DEFF Research Database (Denmark)

Küter, André; Geiker, Mette Rica; Olesen, John Forbes

2005-01-01

was similar for both sets and the maximum crack width was kept constant throughout the exposure period by means of precracking and an external prestressed reinforcement. Chloride profiles after 40 days revealed a considerable increase in ingress towards the crack tip in contrast to data from the literature....... Preliminary investigations have been undertaken to quantify the effect of dynamic load application on the chloride ingress into concrete cracks. Specimens were designed allowing ingress of a chloride solution into a single crack of a saturated unreinforced mortar beam. One set of specimens was subjected...... to a load frequency of ten applications per minute and a second set to one application per hour simulating static cracks, however limiting the ingress hampering effects of autogenous healing and a possible dense precipitation on the crack faces. The averaged chloride exposure interval of the crack faces...

Chloride ingress profiles measured by electron probe micro analysis

DEFF Research Database (Denmark)

Jensen, Ole mejlhede; Coats, Alison M.; Glasser, Fred P.

1996-01-01

Traditional techniques for measuring chloride ingress profiles do not apply well to high performance cement paste systems; the geometric resolution of the traditional measuring techniques is too low. In this paper measurements by Electron Probe Micro Analysis (EPMA) are presented. EPMA is demonst......Traditional techniques for measuring chloride ingress profiles do not apply well to high performance cement paste systems; the geometric resolution of the traditional measuring techniques is too low. In this paper measurements by Electron Probe Micro Analysis (EPMA) are presented. EPMA...... is demonstated to determine chloride ingress in cement paste on a micrometer scale. Potential chloride ingress routes such as cracks or the paste-aggregate interface may also be characterized by EPMA. Copyright (C) 1996 Elsevier Science Ltd...

Prime Example Ingress Reframing the Pervasive Game Design Framework (PGDF

Directory of Open Access Journals (Sweden)

Heinrich Söbke

2017-06-01

Full Text Available The growing availability of mobile communication infrastructure over the last decade has contributed significantly to the maturity of Pervasive Gaming. The massive success of games such as Ingress and Pokémon Go made pervasive gaming a viable option for transforming learning. By its adaptability to location and context, pervasive technology is a valuable support for the design of engaging learning experiences. Despite profound examples of pervasive gaming as learning tool, there is still a lack of reliable methodologies to construct purposeful pervasive learning experiences. The Pervasive Game Design Framework (PGDF is intended to fill this gap. In this article, we present the PGDF using the example of Ingress. Ingress is a prominent pervasive game, as it has received huge attention since its appearance in 2012. A large community of players and third-party-tool suppliers has created a rich set of experiences since then. In this research, we examine Ingress according to PGDF’s categories based on a survey among long-term Ingress players (N=133. Founded on this analysis we identify three main benefits for Ingress players. Furthermore, we discuss the consequences of these findings on the PGDF. Summarizing, this work strengthens the applicability of the PGDF, in order to enable the construction of enriched pervasive learning experiences.

The study on water ingress mass in the steam generator heat-exchange tube rupture accident of modular high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Wang Yan; Shi Lei; Li Fu; Zheng Yanhua

2012-01-01

The steam generator heat-exchange tube rupture (SGTR) accident is an important and particular accident which will result in water ingress to the primary loop of reactor. Water ingress will result in chemical reaction of graphite fuel and structure with water, which may cause overpressure due to generation of explosive gaseous in large quantity. The study on the water ingress accident is significant for the verification of the inherent characteristics of high temperature gas-cooled reactor. The previous research shows that the amount of water ingress mass is the dominant key factor on the severity of the accident consequence. The 200 MWe high temperature gas-cooled reactor (HTR-PM), which is the first modular pebble-bed high temperature gas-cooled reactor in China designed by the Institute of Nuclear and New Energy Technology of Tsinghua University, is selected to be analyzed in this paper. The different DBA accident scenarios of double-ended break of single heat-exchange tube are simulated respectively by the thermal-hydraulic analysis code RETRAN-02. The results show the water ingress mass through the broken heat-exchange tube is related to the break location. The amount of water ingress mass is affected obviously by the capacity of the emptier system. With the balance of safety and economical efficiency, the amount of water ingress mass from the secondary side of steam generator into the primary coolant loop will be reduced by increasing properly the diameter of the draining lines. (authors)

Inhibition of oxidation in nuclear graphite

International Nuclear Information System (INIS)

Winston, Philip L.; Sterbentz, James W.; Windes, William E.

2015-01-01

Graphite is a fundamental material of high-temperature gas-cooled nuclear reactors, providing both structure and neutron moderation. Its high thermal conductivity, chemical inertness, thermal heat capacity, and high thermal structural stability under normal and off-normal conditions contribute to the inherent safety of these reactor designs. One of the primary safety issues for a high-temperature graphite reactor core is the possibility of rapid oxidation of the carbon structure during an off-normal design basis event where an oxidising atmosphere (air ingress) can be introduced to the hot core. Although the current Generation IV high-temperature reactor designs attempt to mitigate any damage caused by a postulated air ingress event, the use of graphite components that inhibit oxidation is a logical step to increase the safety of these reactors. Recent experimental studies of graphite containing between 5.5 and 7 wt% boron carbide (B 4 C) indicate that oxidation is dramatically reduced even at prolonged exposures at temperatures up to 900 deg. C. The proposed addition of B 4 C to graphite components in the nuclear core would necessarily be enriched in B-11 isotope in order to minimise B-10 neutron absorption and graphite swelling. The enriched boron can be added to the graphite during billet fabrication. Experimental oxidation rate results and potential applications for borated graphite in nuclear reactor components will be discussed. (authors)

Supply Ventilation and Prevention of Carbon Monoxide (II) Ingress into Building Premises

Science.gov (United States)

Litvinova, N. A.

2017-11-01

The article contains the relationships of carbon monoxide (II) concentration versus height-above-ground near buildings derived based on results of studies. The results of studies are crucial in preventing external pollutants ingress into a ventilation system. Being generated by external emission sources, such as motor vehicles and city heating plants, carbon monoxide (II) enters the premises during operation of a supply ventilation system. Fresh air nomographic charts were drawn to select the height of a fresh air intake into the ventilation system. Nomographic charts take into account external sources. The selected emission sources are located at various levels above ground relative to the building. The recommendations allow designing supply ventilation taking into account the quality of ambient air through the whole building height.

Water Ingress Testing of the Turbula Jar and U-233 Lead Pig Containers

Energy Technology Data Exchange (ETDEWEB)

Reeves, Kirk Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karns, Tristan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Smith, Paul Herrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-11-02

Understanding the water ingress behavior of containers used at the TA-55 Plutonium Facility has significant implications for criticality safety. The purpose of this report is to document the water ingress behavior of the Turbula Jar with Bakelite lid and Viton gaskets (Turbula Jar) used in oxide blending operations and the U-233 lead pig container used to store and transport U-233 material. The technical basis for water resistant containers at TA-55 is described in LA-UR-15-22781, “Water Resistant Container Technical Basis Document for the TA-55 Criticality Safety Program.” Testing of the water ingress behavior of various containers is described in LA-CP-13-00695, “Water Penetration Tests on the Filters of Hagan and SAVY Containers,” LA-UR-15-23121, “Water Ingress into Crimped Convenience Containers under Flooding Conditions,” and in LA-UR- 16-2411, “Water Ingress Testing for TA-55 Containers.” Water ingress criteria are defined in TA55-AP-522 “TA-55 Criticality Safety Program”, and in PA-RD-01009 “TA55 Criticality Safety Requirements.” The water ingress criteria for submersion is no more than 50 ml of water ingress at a 6” water column height for a period of 2 hours.

Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Wang, Yan; Zheng, Yanhua; Li, Fu; Shi, Lei

2014-01-01

Water ingress into the primary circuit is generally recognized as one of the severe accidents with potential hazard to the modular high temperature gas-cooled reactor, which will cause a positive reactivity introduction with the increase of steam density in reactor core to enhance neutron slowing-down, also the chemical corrosion of graphite fuel elements and the damage of reflector structure material. The increase of the primary pressure may result in the opening of the safety valves, consequently leading the release of radioactive isotopes and flammable water gas. The research on water ingress transient is significant for the verification of inherent safety characteristics of high temperature gas-cooled reactor. The 200 MWe high temperature gas-cooled reactor (HTR-PM), designed by the Institute of Nuclear and New Energy Technology of Tsinghua University, is exampled to be analyzed in this paper. The design basis accident (DBA) scenarios of double-ended guillotine break of single heat-exchange tube (steam generator heat-exchange tube rupture) are simulated by the thermal-hydraulic analysis code, and some key concerns which are relative to the amount of water into the reactor core during the blow-down transient are analyzed in detail. The results show that both of water mass and steam ratio of the fluid spouting from the broken heat-exchange tube are affected by break location, which will increase obviously with the broken location closing to the outlet of the heat-exchange tube. The double-ended guillotine rupture at the outlet of the heat-exchange will result more steam penetrates into the reactor core in the design basis accident of water ingress. The mass of water ingress will also be affected by the draining system. It is concluded that, with reasonable optimization on design to balance safety and economy, the total mass of water ingress into the primary circuit of reactor could be limited effectively to meet the safety requirements, and the pollution of

Chloride Ingress into Concrete under Water Pressure

DEFF Research Database (Denmark)

Lund, Mia Schou; Sander, Lotte Braad; Grelk, Bent

2011-01-01

The chloride ingress into concrete under water pressures of 100 kPa and 800 kPa have been investigated by experiments. The specimens were exposed to a 10% NaCl solution and water mixture. For the concrete having w/c = 0.35 the experimental results show the chloride diffusion coefficient at 800 k......Pa (～8 atm.) is 12 times greater than at 100 kPa (～1 atm.). For w/c = 0.45 and w/c = 0.55 the chloride diffusion coefficients are 7 and 3 times greater. This means that a change in pressure highly influences the chloride ingress into the concrete and thereby the life length models for concrete structures....

HTGR [High Temperature Gas-Cooled Reactor] ingress analysis using MINET

International Nuclear Information System (INIS)

Van Tuyle, G.J.; Yang, J.W.; Kroeger, P.G.; Mallen, A.N.; Aronson, A.L.

1989-04-01

Modeling of water/steam ingress into the primary (helium) cooling circuit of a High Temperature Gas-Cooled Reactor (HTGR) is described. This modeling was implemented in the MINET Code, which is a program for analyzing transients in intricate fluid flow and heat transfer networks. Results from the simulation of a water ingress event postulated for the Modular HTGR are discussed. 27 refs., 6 figs., 6 tabs

Screening of Low Clinker Binders, Compressive Strength and Chloride Ingress

DEFF Research Database (Denmark)

Geiker, Mette Rica; De Weerdt, Klaartje; Garzón, Sergio Ferreiro

2017-01-01

This paper reports an initial screening of potential new binders for concrete with reduced CO2-emission. Mortars cured saturated for 90 days are compared with regard to a) compressive strength of mortars with similar water-to-binder ratio, and b) chloride ingress in similar design strength mortar...... compromising the 90 days compressive strength and resistance to chloride ingress in marine exposure by using selected alternative binders....

Some perspective decisions for the regeneration system equipment of the thermal and nuclear power plants decreasing the probability of water ingress into the turbine and rotor acceleration by return steam flow

Science.gov (United States)

Trifonov, N. N.; Svyatkin, F. A.; Sintsova, T. G.; Ukhanova, M. G.; Yesin, S. B.; Nikolayenkova, E. K.; Yurchenko, A. Yu.; Grigorieva, E. B.

2016-03-01

The regeneration system heaters are one of the sources of possible ingress of the water into the turbine. The water penetrates into the turbine either at the heaters overflow or with the return flow of steam generated when the water being in the heater boils up in the dynamic operation modes or at deenergization of the power-generating unit. The return flow of steam and water is dangerous to the turbine blades and can result in the rotor acceleration. The known protective devices used to prevent the overflow of the low-pressure and high-pressure heaters (LPH and HPH), of the horizontal and vertical heaters of heating-system water (HWH and VWH), as well as of the deaerators and low-pressure mixing heaters (LPMH) were considered. The main protective methods of the steam and water return flows supplied by the heaters in dynamic operation modes or at deenergization of the power-generating unit are described. Previous operating experience shows that the available protections do not fully prevent water ingress into the turbine and the rotor acceleration and, therefore, the development of measures to decrease the possibility of ingress of the water into the turbine is an actual problem. The measures allowing eliminating or reducing the water mass in the heaters are expounded; some of them were designed by the specialists of OAO Polzunov Scientific and Development Association on Research and Design of Power Equipment (NPO CKTI) and are efficiently introduced at heat power plants and nuclear power plants. The suggested technical solutions allow reducing the possibility of the water ingress into the turbine and rotor acceleration by return steam flow in the dynamic operation modes or in the case of power generating unit deenergization. Some of these solutions have been tested in experimental-industrial exploitation and can be used in industry.

Ingress of radioactive material into dwellings

International Nuclear Information System (INIS)

Roed, J.; Goddard, A.J.H.

1991-01-01

People inside buildings will normally obtain some protection against airborne pollution originating in the outdoor air. This protection will be due to deposition indoors on floors, walls, ceilings and furniture, and to filtration during ingress, in cracks, crevices and pores in the building structure. A building will also give some protection against direct gamma radiation from outdoor deposits on the ground and external building surfaces. However, indoor deposits, while reducing air exposure, may add to the dose commitment from direct gamma radiation. Other subsidiary factors such as mechanical transport may need to be considered. We used test houses for finding factors by which outdoor air concentrations exceed those found indoors. Be-7 of cosmogenic origin and associated with natural aerosol has been used as a tracer, together with radionuclides dispersed in the atmosphere as a result of the Chernobyl accident. In addition, SF 6 tracer measurements have been used to measure air exchange rates. Novel experimental arrangements, to isolate the deposition process, were used. Attention has also been given to developing suitable tracers for monodisperse artificial aerosols and to means of detecting such aerosols. The use of these techniques in studying mechanical transport of particulate material is described. The indoor to outdoor airborne concentration ratios in a test house during the Chernobyl accident were found to be 0.25 for caesium, 0.4 for particulate iodine and 0.5 for beryllium-7. Indoor deposition velocities, for a range of radionuclides, ranged from 7 10-5 to 2 10-4 m s-1. Subsequently, aerosol deposition measurements were conducted in unfurnished, partly furnished and fully furnished houses, using Be-7 as a tracer. Measured deposition velocities ranged from 10-5 m s-1 for the unfurnished room to 3 10-5 m s-1 for the fully furnished room

Degradation of fly ash concrete under the coupled effect of carbonation and chloride aerosol ingress

International Nuclear Information System (INIS)

Liu, Jun; Qiu, Qiwen; Chen, Xiaochi; Wang, Xiaodong; Xing, Feng; Han, Ningxu; He, Yijian

2016-01-01

Highlights: • Carbonation affects the chloride profile in concrete under chloride aerosol attack. • The chloride binding capacity can be reduced by the presence of carbonation. • Carbonation increases the rate of chloride diffusion for chloride aerosol ingress. • Chloride aerosol ingress reduces the carbonation depth and increases the pH value. • The use of fly ash in concrete enhances the resistance of chloride aerosol ingress. - Abstract: This paper presents an experimental investigation regarding the coupled effect of carbonation and chloride aerosol ingress on the durability performance of fly ash concrete. Test results demonstrate that carbonation significantly affects the chloride ingress profile, reduces the chloride binding capacity, and accelerates the rate of chloride ion diffusion. On the other hand, the carbonation rate of fly ash concrete is reduced by the presence of chlorides aerosol. The interaction nature between concrete carbonation and chloride aerosol ingress is also demonstrated by the microscopic analysis results obtained from scanning electron microscope and mercury intrusion porosimetry.

Nuclear air cleaning

International Nuclear Information System (INIS)

Bellamy, R.R.

1994-01-01

This report briefly describes the history of the use of high- efficiency particulate air filters for air cleaning at nuclear installations in the United States and discusses future uses of such filters

Analysis of helium purification system capability during water ingress accident in RDE

Science.gov (United States)

Sriyono; Kusmastuti, Rahayu; Bakhri, Syaiful; Sunaryo, Geni Rina

2018-02-01

The water ingress accident caused by steam generator tube rupture (SGTR) in RDE (Experimental Power Reactor) must be anticipated. During the accident, steam from secondary system diffused and mixed with helium gas in the primary coolant. To avoid graphite corrosion in the core, steam will be removed by Helium purification system (HPS). There are two trains in HPS, first train for normal operation and the second for the regeneration and accident. The second train is responsible to clean the coolant during accident condition. The second train is equipped with additional component, i.e. water cooler, post accident blower, and water separator to remove this mixture gas. During water ingress, the water release from rupture tube is mixed with helium gas. The water cooler acts as a steam condenser, where the steam will be separated by water separator from the helium gas. This paper analyses capability of HPS during water ingress accident. The goal of the research is to determine the time consumed by HPS to remove the total amount of water ingress. The method used is modelling and simulation of the HPS by using ChemCAD software. The BDBA and DBA scenarios will be simulated. In BDBA scenario, up to 110 kg of water is assumed to infiltrate to primary coolant while DBA is up to 35 kg. By using ChemCAD simulation, the second train will purify steam ingress maximum in 0.5 hours. The HPS of RDE has a capability to anticipate the water ingress accident.

Literature investigation of air/steam ingress through small cracks in concrete wall under pressure differences

International Nuclear Information System (INIS)

Jiang, J.T.

2008-01-01

Traditionally within CANDU safety analysis, a loss coefficient of ∼2.8 is used to characterize turbulent flow leakage through narrow, sharp-edged cracks into, and out of Steam Protected Rooms (SPRs). In the event of main steam line break (MSLB), the pressure differences observed between SPRs and the surrounding area of the powerhouse range from 0.01kPa to 0.1 kPa. The relatively low pressure differences, coupled with narrow crack sizes, for instance, below 1 mm, may result in laminar flow leakage pathways as opposed to the turbulent variety assumed in analysis. The main purpose of this paper is thus (a) to calculate the loss coefficient for laminar flow through small cracks; and (b) to assess the effect of steam ingress to SPRs when the flow through some or all of the room leakage area is assumed to be laminar. Based on the literature review, the loss coefficient for laminar flow, through 1 mm crack size at 0.1 kPa pressure difference, ranges from 10 to about 65. This value represents an increase in loss coefficient of 3 ∼ 22 times the loss coefficient used for SPR safety analysis. The actual volumetric leakage rate is therefore 3 ∼ 8 times smaller than the amount previously applied. This paper demonstrates how the traditional loss coefficient used in safety analysis is extremely conservative in the analysis of the SPRs steam ingress phenomenon. (author)

Literature investigation of air/steam ingress through small cracks in concrete wall under pressure differences

Energy Technology Data Exchange (ETDEWEB)

Jiang, J.T. [McMaster Univ., Engineering Physics Dept., Hamilton, Ontario (Canada)], E-mail: jiangj3@mcmaster.ca

2008-07-01

Traditionally within CANDU safety analysis, a loss coefficient of {approx}2.8 is used to characterize turbulent flow leakage through narrow, sharp-edged cracks into, and out of Steam Protected Rooms (SPRs). In the event of main steam line break (MSLB), the pressure differences observed between SPRs and the surrounding area of the powerhouse range from 0.01kPa to 0.1 kPa. The relatively low pressure differences, coupled with narrow crack sizes, for instance, below 1 mm, may result in laminar flow leakage pathways as opposed to the turbulent variety assumed in analysis. The main purpose of this paper is thus (a) to calculate the loss coefficient for laminar flow through small cracks; and (b) to assess the effect of steam ingress to SPRs when the flow through some or all of the room leakage area is assumed to be laminar. Based on the literature review, the loss coefficient for laminar flow, through 1 mm crack size at 0.1 kPa pressure difference, ranges from 10 to about 65. This value represents an increase in loss coefficient of 3 {approx} 22 times the loss coefficient used for SPR safety analysis. The actual volumetric leakage rate is therefore 3 {approx} 8 times smaller than the amount previously applied. This paper demonstrates how the traditional loss coefficient used in safety analysis is extremely conservative in the analysis of the SPRs steam ingress phenomenon. (author)

Chloride ingress in cement paste and mortar measured by Electron Probe Micro Analysis

DEFF Research Database (Denmark)

Jensen, Ole Mejlhede

1998-01-01

is an important basis for designing the durability of concrete structures. As an example the Danish Great Belt link is designed to have 100 years durability based on calculation of chloride ingress.During the last 15 years the types of concrete used in practice have changed substantially. Due to plasticizers......Chloride ingress is a common cause of deterioration of reinforced concrete structures. Concrete may be exposed to chloride by sea water or deicing salts. The chloride initiates corrosion of the reinforcement which through expansion disrupts the concrete. Modelling the chloride ingress...... and mineral additives concretes with higher strengths and reduced permeability are produced. Recently it has become clear that traditional chloride ingress models do not apply to modern concretes. Actually, the life time model used for the Danish Great Belt link has shown up to be based on wrong assumptions...

Numerical simulation of severe water ingress accidents in a modular high temperature gas cooled reactor

International Nuclear Information System (INIS)

Zhang Zuoyi; Scherer, W.

1996-01-01

This report analyzes reverse water ingress accidents in the SIEMENS 200 MW Modular Pebble-Bed High Temperature Gas Cooled Reactor (HTR-MODULE) under the assumption of no active safety protection systems in order to find the safety margins of the current HTR-MODULE design and to realize a catastrophe-free nuclear technology. A water, steam and helium multi-phase cavity model is developed and implemented in the DSNP simulation system. The DSNP system is then used to simulate the primary and secondary circuit of a HTR-MODULE power plant. Comparisons of the model with experiments and with TINTE calculations serve as validation of the simulation. The analysis of the primary circuit tries to answer the question how fast the water enters the reactor core. It was found that the maximum H 2 O concentration increase in the reactor core is smaller than 0.3 kg/(m 3 s). The liquid water vaporization in the steam generator and H 2 O transport from the steam generator to the reactor core reduce the ingress velocity of the H 2 O into the reactor core. In order to answer the question how much water enters the primary circuit, the full cavitation of the feed water pumps is analyzed. It is found that if the secondary circuit is depressurized enough, the feed water pumps will be inherently stopped by the full cavitation. This limits the water to be pumped from the deaerator to the steam generator. A comprehensive simulation of the MODUL-HTR power plant then shows that the H 2 O inventory in the primary circuit can be limited to about 3000 kg. The nuclear reactivity increase caused by the water ingress leads to a fast power excursion, which, however, is inherently counterbalanced by negative feedback effects. Concerning the integrity of the fuel elements, the safety relevant temperature limit of 1600 C was not reached in any case. (orig.) [de

A separate effect study of the influence of metallic fission products on CsI radioactive release from nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Di Lemma, F.G., E-mail: fidelma.dilemma@gmail.com [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University of Technology, Delft, 2629 JB (Netherlands); Colle, J.Y., E-mail: jean-yves.colle@ec.europa.eu [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Beneš, O. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Konings, R.J.M. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University of Technology, Delft, 2629 JB (Netherlands)

2015-10-15

The chemistry of cesium and iodine is of main importance to quantify the radioactive release in case of a nuclear reactor accident, or sabotage involving irradiated nuclear materials. We studied the interaction of CsI with different metallic fission products such as Mo and Ru. These elements can be released from nuclear fuel when exposed to oxidising conditions, as in the case of contact of overheated nuclear fuel with air (e.g. in a spent fuel cask sabotage, uncovering of a spent fuel pond, or air ingress accidents). Experiments were performed by vaporizing mixtures of the compounds in air, and analysing the produced aerosols in view of a possible gas–gas and gas–aerosol reactions between the compounds. These results were compared with the gaseous species predicted by thermochemical equilibrium calculations and experimental equilibrium vaporization tests using Knudsen Effusion Mass Spectrometry.

Mitigation of corrosion product ingress into SG's

International Nuclear Information System (INIS)

Han, S.H.

1988-01-01

Design and operation experiences to mitigate corrosion product ingress into SGs in Korea nuclear power plants are briefly reviewed. Maintaining the feedwater pH above 9.6 with morpholine seems to contribute significantly to reduction of iron transport to SGs. Measured iron transport rates were 4.8 g/hr/100 MWe at pH 9.8 and 2.8 g/hr/100 MWe at 9.3, respectively. Removal of corrosion products through SG blowdown is very limited. Its removal efficiency at the higher pH plant was in the neighborhood of 10 %. In one of the Korea Nuclear Units, a large amount of sludge piles were found in the middle of tube bundles especially on the cold leg side. Damaged tubes were identified by the multi-frequency eddy current tests and plugged later during the refueling period. Intermittent blowdown-rate increase was tried to enhance ionic impurity removal through SG blowdown. Even though it was not effective against Na, removal other impurity was improved, resulting in prolonged condensate polisher operation periods by 1 - 2 days. Two-bed polisher design, a cation bed followed by a mixed bed, was chosen for future PWR plants to enhance corrosion product filtering capability of the polishers. Condensate pump discharge polishing and divided hot well polishing methods are currently in consideration. (Nogami, K.)

Severe water ingress accident analysis for a Modular High Temperature Gas Cooled Reactor

International Nuclear Information System (INIS)

Zhang Zuoyi; Scherer, Winfried

1997-01-01

This paper analyzes the severe water ingress accidents in the SIEMENS 200MW Modular High Temperature Gas Cooled Reactor (HTR-Module) under the assumption of no active safety protection systems in order to find the safety margin of the current HTR-Module design. A water, steam and helium multi-phase cavity model is originally developed and implemented in the DSNP simulation system. The developed DSNP system is used to simulate the primary circuit of HTR-Module power plant. The comparisons of the models with the TINTE calculations validate the current simulation. After analyzing the effects of blower separation on water droplets, the wall heat storage, etc., it is found that the maximum H 2 O density increase rate in the reactor core is smaller than 0.3 kg/(m 3 s). The liquid water vaporization in the steam generator and H 2 O transport from the steam generator to the reactor core reduces the impulse of the H 2 O in the reactor core. The nuclear reactivity increase caused by the water ingress leads to a fast power excursion, which, however, is inherently counterbalanced by negative feedback effects. Concerning the integrity of the fuel elements, the safety relevant temperature limit of 1600degC was not reached in any case. (author)

Chloride ingress prediction

DEFF Research Database (Denmark)

Frederiksen, Jens Mejer; Geiker, Mette Rica

2008-01-01

Prediction of chloride ingress into concrete is an important part of durability design of reinforced concrete structures exposed to chloride containing environment. This paper presents experimentally based design parameters for Portland cement concretes with and without silica fume and fly ash...... in marine atmospheric and submersed South Scandinavian environment. The design parameters are based on sequential measurements of 86 chloride profiles taken over ten years from 13 different types of concrete. The design parameters provide the input for an analytical model for chloride profiles as function...... of depth and time, when both the surface chloride concentration and the diffusion coefficient are allowed to vary in time. The model is presented in a companion paper....

Effects of the Air Flow Rate on The Oxidation of NBG-18 and 25 Nuclear Graphite Grades

International Nuclear Information System (INIS)

Chi, Se-Hwan; Kim, Gen-Chan; Jang, Joon-Hee

2007-01-01

For a VHTR, graphite oxidation is regarded as a critical phenomenon for degrading the integrity of graphite components under normal or abnormal conditions. The oxidation of a graphite core component can occur by air which may permeate into the primary coolant operation and/or by impurities contained in the He coolant, or by air ingress during a severe accident. It is well known that the oxidation properties of a graphite are highly dependent on the source of raw materials, impurities, microstructures (crystallites, pore structure), and on the processing and environmental parameters, such as the forming methods, the coolant type, moisture and impurity content, temperature, flow rate and the oxygen potential of the coolants. A lot of work has been performed on the oxidation of graphite since the 1960s, and, for example, in the case of the temperature, a widely accepted oxidation model on the effects of a temperature has already been developed. However, in the case of the flow rate, even for its expected effects in a VHTR, for example, as to the expected changes in the bypass flow (10-20 %) during an operation, no systematic works have been performed. In this respect, as a preliminary study, the effects of an air flow rate on the oxidation of NBG-18 and 25 nuclear graphite were investigated

Witwatersrand Water Ingress Project - Information Management System (WWIPIMS), South Africa

Energy Technology Data Exchange (ETDEWEB)

Hild, S.; Sieste, M.; Barth, A.; Rudinskaya, J. [Beak Consultants GmbH, Freiberg (Germany); Croukamp, L.; Roos, M. [Council for Geoscience (CGS), Pretoria (South Africa)

2006-07-01

The Witwatersrand Water Ingress Project at the Council for Geoscience, South Africa (CGS) deals with an inventory, a risk assessment and the development of rehabilitation strategies for abandoned mining sites in the Witwatersrand Mining Basin. The main focus is the prevention of water ingress and to understand the future decanting scenario. An Information Management System consisting of both a relational database and an application for the Witwatersrand Water Ingress Project is established for accessing and managing all project-related data. This easy to use application makes the data available to all staff at the CGS via several modules as well as a GIS-component for accessing and querying spatial data. This will enable the scientists to derive further knowledge of the water flowing processes by directly using all of the existing up-to-date data. Many additional functions, such as the support for map printing on demand, extensive possibilities for inquiries, data import and export, diagrams and a GIS-viewer for spatial inquiries do complete the system. (orig.)

Physics of the pebble-bed high temperature reactor in massive water ingress accidents

International Nuclear Information System (INIS)

Scherer, W.

1989-10-01

A point-kinetics model was developed to describe qualitatively hypothetical water ingress transients in the primary loop of High Temperature Reactors. Neutron kinetics, heat-flow balance and the chemical reaction of graphite corrosion together with their mutual influence are included. The qualitative behaviour of the transients is calculated and discussed for two fictitious examples, namely the long-term water ingress into a medium sized HTR (HTR-500) and the 'startup' of a small HTR after an intensive water flooding of the core. The model developed and the computer code KINKOR are thought to be tools for the general understanding of the water ingress phenomena and should be looked at as basis for more elaborated systems. (orig./HP) [de

The Safety of Hospital Beds: Ingress, Egress, and In-Bed Mobility.

Science.gov (United States)

Morse, Janice M; Gervais, Pierre; Pooler, Charlotte; Merryweather, Andrew; Doig, Alexa K; Bloswick, Donald

2015-01-01

To explore the safety of the standard and the low hospital bed, we report on a microanalysis of 15 patients' ability to ingress, move about the bed, and egress. The 15 participants were purposefully selected with various disabilities. Bed conditions were randomized with side rails up or down and one low bed with side rails down. We explored the patients' use of the side rails, bed height, ability to lift their legs onto the mattress, and ability to turn, egress, and walk back to the chair. The standard bed was too high for some participants, both for ingress and egress. Side rails were used by most participants when entering, turning in bed, and exiting. We recommend that side rails be reconsidered as a means to facilitate in-bed movement, ingress, and egress. Furthermore, single deck height settings for all patients are not optimal. Low beds as a safety measure must be re-evaluated.

Improvement design study on steam generator of MHR-50/100 aiming higher safety level after water ingress accident

International Nuclear Information System (INIS)

Oyama, S.; Minatsuki, I.; Shimizu, K.

2012-01-01

Mitsubishi Heavy Industries, Ltd. (MHI) has been studying on MHI original High Temperature Gas cooled Reactor (HTGR), namely MHR-50/100, for commercialization with supported by JAEA. In the heat transfer system, steam generator (SG) is one of the most important components because it should be imposed a function of heat transfer from reactor power to steam turbine system and maintaining a nuclear grade boundary. Then we especially focused an effort of a design study on the SG having robustness against water ingress accident based on our design experience of PWR, FBR and HTGR. In this study, we carried out a sensitivity analysis from the view point of economic and plant efficiency. As a result, the SG design parameter of helium inlet/outlet temperature of 750 deg. C/300 deg. C, a side-by-side layout and one unit of SG attached to a reactor were selected. In the next, a design improvement of SG was carried out from the view point of securing the level of inherent safety without reliance on active steam dump system during water ingress accident considering the situation of the Fukushima nuclear power plant disaster on March 11, 2011. Finally, according to above basic design requirement to SG, we performed a conceptual design on adapting themes of SG structure improvement. (authors)

Ingress in Geography: Portals to Academic Success?

Science.gov (United States)

Davis, Michael

2017-01-01

Niantic Labs has developed an augmented virtual reality mobile app game called Ingress in which agents must seek out and control locations for their designated factions. The app uses the Google Maps interface along with GPS to enhance a geocaching-like experience with elements of other classical games such as capture-the-flag. This study aims to…

Ventilation-air conditioner system in nuclear power plant

International Nuclear Information System (INIS)

Kubota, Ryuji; Sugisaki, Toshihiko.

1989-01-01

This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

Ingression-type cell migration drives vegetal endoderm internalisation in the Xenopus gastrula.

Science.gov (United States)

Wen, Jason Wh; Winklbauer, Rudolf

2017-08-10

During amphibian gastrulation, presumptive endoderm is internalised as part of vegetal rotation, a large-scale movement that encompasses the whole vegetal half of the embryo. It has been considered a gastrulation process unique to amphibians, but we show that at the cell level, endoderm internalisation exhibits characteristics reminiscent of bottle cell formation and ingression, known mechanisms of germ layer internalisation. During ingression proper, cells leave a single-layered epithelium. In vegetal rotation, the process occurs in a multilayered cell mass; we refer to it as ingression-type cell migration. Endoderm cells move by amoeboid shape changes, but in contrast to other instances of amoeboid migration, trailing edge retraction involves ephrinB1-dependent macropinocytosis and trans -endocytosis. Moreover, although cells are separated by wide gaps, they are connected by filiform protrusions, and their migration depends on C-cadherin and the matrix protein fibronectin. Cells move in the same direction but at different velocities, to rearrange by differential migration.

Experiments on the behaviour of ruthenium in air ingress accidents

International Nuclear Information System (INIS)

Kaerkelae, T.; Backman, Ul; Auvinen, A.; Zilliacus, R.; Lipponen, M.; Kekki, T.; Tapper, U.; Jokiniemi, J.

2007-03-01

During routine nuclear reactor operation, ruthenium will accumulate in the fuel in relatively high concentrations. In a severe accident in a nuclear power plant it is possible that air gets into contact with the reactor core. In this case ruthenium may oxidise and form volatile ruthenium species, RuO3 and RuO4, which can be transported into the containment. In order to estimate the amount of gaseous ruthenium species, it is of interest to know, how they are formed and how they behave. In our experiments the formation and transport of volatile ruthenium oxides was studied by exposing RuO2 powder to diverse oxidising atmospheres at a relatively high temperature. Transport of gaseous RuO4 was further investigated by injecting it into the facility in similar conditions. Upon cooling of the gas flow RuO2 aerosol particles were formed in the system. They were removed from the gas stream with plane filters. Gaseous ruthenium species were trapped in 1M NaOH-water solution, which is capable of trapping RuO4 totally. Ruthenium in the solution was filtered for analysis. The determination of ruthenium both in aerosol and in liquid filters was made using instrumental neutron activation analysis (INAA). In order to close the mass balance and to achieve better time resolution seven experiment were carried out using radioactive tracer. In this report, the facility for the ruthenium behaviour study and results from experiments are presented. Preliminary conclusions from the experiments are reported as well. Final conclusions will be made after modelling of the facility is completed in a continuation work of this study. (au)

Experiments on the behaviour of ruthenium in air ingress accidents

Energy Technology Data Exchange (ETDEWEB)

Kaerkelae, T.; Backman, Ul; Auvinen, A.; Zilliacus, R.; Lipponen, M.; Kekki, T.; Tapper, U.; Jokiniemi, J. [Technical Research Centre of Finland VTT (Finland)

2007-03-15

During routine nuclear reactor operation, ruthenium will accumulate in the fuel in relatively high concentrations. In a severe accident in a nuclear power plant it is possible that air gets into contact with the reactor core. In this case ruthenium may oxidise and form volatile ruthenium species, RuO3 and RuO4, which can be transported into the containment. In order to estimate the amount of gaseous ruthenium species, it is of interest to know, how they are formed and how they behave. In our experiments the formation and transport of volatile ruthenium oxides was studied by exposing RuO2 powder to diverse oxidising atmospheres at a relatively high temperature. Transport of gaseous RuO4 was further investigated by injecting it into the facility in similar conditions. Upon cooling of the gas flow RuO2 aerosol particles were formed in the system. They were removed from the gas stream with plane filters. Gaseous ruthenium species were trapped in 1M NaOH-water solution, which is capable of trapping RuO4 totally. Ruthenium in the solution was filtered for analysis. The determination of ruthenium both in aerosol and in liquid filters was made using instrumental neutron activation analysis (INAA). In order to close the mass balance and to achieve better time resolution seven experiment were carried out using radioactive tracer. In this report, the facility for the ruthenium behaviour study and results from experiments are presented. Preliminary conclusions from the experiments are reported as well. Final conclusions will be made after modelling of the facility is completed in a continuation work of this study. (au)

Chloride Ingress in Chemically Activated Calcined Clay-Based Cement

Directory of Open Access Journals (Sweden)

Joseph Mwiti Marangu

2018-01-01

Full Text Available Chloride-laden environments pose serious durability concerns in cement based materials. This paper presents the findings of chloride ingress in chemically activated calcined Clay-Ordinary Portland Cement blended mortars. Results are also presented for compressive strength development and porosity tests. Sampled clays were incinerated at a temperature of 800°C for 4 hours. The resultant calcined clay was blended with Ordinary Portland Cement (OPC at replacement level of 35% by mass of OPC to make test cement labeled PCC35. Mortar prisms measuring 40 mm × 40 mm × 160 mm were cast using PCC35 with 0.5 M Na2SO4 solution as a chemical activator instead of water. Compressive strength was determined at 28th day of curing. As a control, OPC, Portland Pozzolana Cement (PPC, and PCC35 were similarly investigated without use of activator. After the 28th day of curing, mortar specimens were subjected to accelerated chloride ingress, porosity, compressive strength tests, and chloride profiling. Subsequently, apparent diffusion coefficients (Dapp were estimated from solutions to Fick’s second law of diffusion. Compressive strength increased after exposure to the chloride rich media in all cement categories. Chemically activated PCC35 exhibited higher compressive strength compared to nonactivated PCC35. However, chemically activated PCC35 had the least gain in compressive strength, lower porosity, and lower chloride ingress in terms of Dapp, compared to OPC, PPC, and nonactivated PCC35.

Prediction of chloride ingress and binding in cement paste

DEFF Research Database (Denmark)

Geiker, Mette Rica; Nielsen, Erik Pram; Herforth, Duncan

2007-01-01

This paper summarizes recent work on an analytical model for predicting the ingress rate of chlorides in cement-based materials. An integral part of this is a thermodynamic model for predicting the phase equilibria in hydrated Portland cement. The model’s ability to predict chloride binding...... in Portland cement pastes at any content of chloride, alkalis, sulfates and carbonate was verified experimentally and found to be equally valid when applied to other data in the literature. The thermodynamic model for predicting the phase equilibria in hydrated Portland cement was introduced into an existing...... Finite Difference Model for the ingress of chlorides into concrete which takes into account its multi-component nature. The “composite theory” was then used to predict the diffusivity of each ion based on the phase assemblage present in the hydrated Portland cement paste. Agreement was found between...

French gas cooled reactor experience with moisture ingress

International Nuclear Information System (INIS)

Bastien, D.; Brie, M.

1995-01-01

During the history of operation of six gas cooled reactors in France, some experience has been gained with accidental water ingress into the primary system. This occurred as a result of leaks in steam generators. This paper describes the cause of the leaks, and the resulting consequences. (author). 2 refs, 8 figs

Contaminant ingress into multizone buildings: An analytical state-space approach

KAUST Repository

Parker, Simon; Coffey, Chris; Gravesen, Jens; Kirkpatrick, James; Ratcliffe, Keith; Lingard, Bryan; Nally, James

2013-01-01

The ingress of exterior contaminants into buildings is often assessed by treating the building interior as a single well-mixed space. Multizone modelling provides an alternative way of representing buildings that can estimate concentration time

Air filters for use at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Linder, P [Aktiebolaget Atomenergi, Studsvik, Nykoeping (Sweden)

1970-12-01

The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment.

Air filters for use at nuclear facilities

International Nuclear Information System (INIS)

Linder, P.

1970-01-01

The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment

Experiments on the behaviour of ruthenium in air ingress accidents - Progress report

International Nuclear Information System (INIS)

Kaerkelae, T.; Backman, U.; Auvinen, A.; Ziliacus, R.; Lipponen, M.; Kekki, T.; Tapper, U.; Jokiniemi, J.

2006-02-01

During routine nuclear reactor operation, ruthenium will accumulate in the fuel in relatively high concentrations. In an accident in a nuclear power plant it is possible that air gets into contact with the reactor core. In this case ruthenium can oxidise and form volatile ruthenium species, RuO3 and RuO4, which can be transported into the containment. In order to estimate the amount of gaseous ruthenium species it is of interest to know, how it is formed and how it behaves. In our experiments RuO2 is exposed to diverse oxidising atmospheres at a relatively high temperature. In this report, the experimental system for the ruthenium behaviour study is presented. Also preliminary results from experiments carried out during year 2005 are reported. In the experiments gaseous ruthenium oxides were produced in a furnace. Upon cooling RuO2 aerosol particles were formed in the system. They were removed with plane filters from the gas stream. Gaseous ruthenium species were trapped in 1M NaOH-water solution, which is capable of trapping RuO4 totally. Ruthenium in the solution was filtered for analysis. The determination of ruthenium both in aerosol and in liquid filters was made using instrumental neutron activation analysis (INAA). In order to close mass balance and achieve better time resolution three experiment using radioactive tracer were carried out. (au)

Experiments on the behaviour of ruthenium in air ingress accidents - Progress report

Energy Technology Data Exchange (ETDEWEB)

Kaerkelae, T.; Backman, U.; Auvinen, A.; Ziliacus, R.; Lipponen, M.; Kekki, T.; Tapper, U.; Jokiniemi, J. [VTT Technical Research Centre of Finland (Finland)

2006-02-15

During routine nuclear reactor operation, ruthenium will accumulate in the fuel in relatively high concentrations. In an accident in a nuclear power plant it is possible that air gets into contact with the reactor core. In this case ruthenium can oxidise and form volatile ruthenium species, RuO3 and RuO4, which can be transported into the containment. In order to estimate the amount of gaseous ruthenium species it is of interest to know, how it is formed and how it behaves. In our experiments RuO2 is exposed to diverse oxidising atmospheres at a relatively high temperature. In this report, the experimental system for the ruthenium behaviour study is presented. Also preliminary results from experiments carried out during year 2005 are reported. In the experiments gaseous ruthenium oxides were produced in a furnace. Upon cooling RuO2 aerosol particles were formed in the system. They were removed with plane filters from the gas stream. Gaseous ruthenium species were trapped in 1M NaOH-water solution, which is capable of trapping RuO4 totally. Ruthenium in the solution was filtered for analysis. The determination of ruthenium both in aerosol and in liquid filters was made using instrumental neutron activation analysis (INAA). In order to close mass balance and achieve better time resolution three experiment using radioactive tracer were carried out. (au)

Fission product release by fuel oxidation after water ingress

International Nuclear Information System (INIS)

Schreiber.

1990-01-01

On the basis of data obtained by a literature search, a computer code has been established for the calculation of the degree of oxidation of the fuel in the damaged fuel particles, and hence of the fission product release as a function of the time period of steam ingress. (orig.) [de

SR-Site: Oxygen ingress in the rock at Forsmark during a glacial cycle

Energy Technology Data Exchange (ETDEWEB)

Sidborn, Magnus (Kemakta Konsult AB (Sweden)); Sandstroem, Bjoern (WSP Sverige AB (Sweden)); Tullborg, Eva-Lena (Terralogica AB (Sweden)); Salas, Joaquin; Maia, Flavia; Delos, Anne; Molinero, Jorge (Amphos21 (Spain)); Hallbeck, Lotta; Pedersen, Karsten (Microbial Analytics Sweden AB (Sweden))

2010-11-15

The aim of this report is to assess the possibility for oxygen to be transported by glacial melt-water to canister positions in a final repository for spent nuclear fuel at the proposed location in Forsmark. The approach for this assessment is to combine reactive transport modelling with geological observations of present and historical indications of oxygen ingress. For safety assessment purposes a cautious approach in the modelling is required when estimating the extent of oxygen ingress. In this report, a cautious approach has been applied both in the conceptualisation of the problem and in the choice of input parameters used in the models. Oxygen consuming processes are only neglected in the modelling if they are expected to further decrease the extent of oxygen ingress. Several oxygen consuming processes have been identified, each of which may play an important role in the scavenging of oxygen along recharge flow paths in the rock. These processes include biological pathways with degradation of organic material of ground surface origin, and biotically mediated reactions with reduced rock minerals and with various materials expected to be present in the backfilled repository volume. In the absence of microbes most of these reactions may also follow abiotic pathways. Present day observations show that degradation of organic material is the most powerful oxygen scavenging process. At Forsmark, oxygen is generally depleted within a few metres under present day temperate conditions. Although biological activity is likely to exist also during different phases of a glaciation, large uncertainties exist regarding e.g. the population growth dynamics, the biotic reaction rates and the availability of organic material under the highly varying conditions expected. Microbial activity and degradation of organic material is therefore pessimistically neglected in the calculations in this report. In the absence of organic material, ferrous iron present in minerals in the rock

SR-Site: Oxygen ingress in the rock at Forsmark during a glacial cycle

International Nuclear Information System (INIS)

Sidborn, Magnus; Sandstroem, Bjoern; Tullborg, Eva-Lena; Salas, Joaquin; Maia, Flavia; Delos, Anne; Molinero, Jorge; Hallbeck, Lotta; Pedersen, Karsten

2010-11-01

The aim of this report is to assess the possibility for oxygen to be transported by glacial melt-water to canister positions in a final repository for spent nuclear fuel at the proposed location in Forsmark. The approach for this assessment is to combine reactive transport modelling with geological observations of present and historical indications of oxygen ingress. For safety assessment purposes a cautious approach in the modelling is required when estimating the extent of oxygen ingress. In this report, a cautious approach has been applied both in the conceptualisation of the problem and in the choice of input parameters used in the models. Oxygen consuming processes are only neglected in the modelling if they are expected to further decrease the extent of oxygen ingress. Several oxygen consuming processes have been identified, each of which may play an important role in the scavenging of oxygen along recharge flow paths in the rock. These processes include biological pathways with degradation of organic material of ground surface origin, and biotically mediated reactions with reduced rock minerals and with various materials expected to be present in the backfilled repository volume. In the absence of microbes most of these reactions may also follow abiotic pathways. Present day observations show that degradation of organic material is the most powerful oxygen scavenging process. At Forsmark, oxygen is generally depleted within a few metres under present day temperate conditions. Although biological activity is likely to exist also during different phases of a glaciation, large uncertainties exist regarding e.g. the population growth dynamics, the biotic reaction rates and the availability of organic material under the highly varying conditions expected. Microbial activity and degradation of organic material is therefore pessimistically neglected in the calculations in this report. In the absence of organic material, ferrous iron present in minerals in the rock

Progress in standards for nuclear air and gas treatment

International Nuclear Information System (INIS)

Burchsted, C.A.

1978-01-01

Standardization in nuclear air and gas treatment spans a period of more than 25 years, starting with military specifications for HEPA filters and filter media, and now progressing to the development of a formal code analogous to the ASME Boiler and Pressure Vessel Code. Whereas the current standard for components and installation of nuclear air cleaning systems is limited to safety related facilities for nuclear power plants, the proposed code will cover all types of critical ventilation and air and gas treatment installations for all types of nuclear facilities

Technical Issues Associated with Air Ingression During Core Degradation

International Nuclear Information System (INIS)

Powers, Dana A.

2000-01-01

This paper has shown that it is possible to get significant air intrusion into a ruptured reactor vessel even from a reactor cavity with restricted access. This suggests that there is some importance to considering the consequences of air intrusion following vessel penetration by core debris. The consequences will depend on the nature of core degradation in air and other oxidizing gases. If, indeed, fuel becomes exposed to strongly oxidizing gases, significant releases of ruthenium and hexavalent urania can be expected. Hexavalent urania could alter the nature of cesium release and cesium revaporization from the reactor coolant system. Hexavalent urania could destabilize CSI and enhance the formation of gaseous iodine unless there are other materials that will react readily with atomic iodine along the flow path to the reactor containment

Durable concrete for a waste repository - Measurement of ionic ingress

International Nuclear Information System (INIS)

Feldman, R.F.; Beaudoin, J.J.; Philipose, K.E.

1990-01-01

A waste repository for the below ground disposal of low level radioactive waste is planned at Chalk River Nuclear Laboratories. It relies greatly on the durability of concrete for the required 500 year service life. A research program to design durable concrete and predict its service life is in progress. The degradation of the concrete depends to a large extent on the rate of ingress of corrosive agents. Penetration of chloride and sulfate ions are particularly relevant. Twenty mix formulations were developed to create various types and qualities of concrete, and to study their behavior in different site environmental conditions. A total of 1,000 concrete specimens are being exposed at 20C and 45C to 25 different combinations of the corrosive agents including CO 2 . Procedures to measure the ionic profiles and to determine the factors controlling diffusion of the ions in the various concretes have been developed. Results of selected concrete systems exposed to chloride and sulfate solutions for 1 year are presented and discussed in terms of pore structure and permeability parameters of the concrete

Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference

International Nuclear Information System (INIS)

First, M.W.; Harvard Univ., Boston, MA

1991-02-01

Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

Suppressing hydrogen ingress during aqueous corrosion of CANDU Zr-2.5 Nb pressure tube material

International Nuclear Information System (INIS)

Elmoselhi, M.B.; Donner, A.; Brennenstuhl, A.; Warr, B.D.; Ellis, P.J.; Evans, D.W.

2002-01-01

As a result of their special properties, including low neutron cross-section and intrinsic corrosion resistance, Zr alloys are used in the fabrication of nuclear core components, particularly fuel cladding (in most reactor types) and also Zr-2.5 Nb pressure tubes in CANDU trademark (Canada Deuterium Uranium) reactors. Corrosion and H uptake during service can limit the life of these components. Therefore, remedial action may be appropriate to slow the H uptake rate and prolong the working life of these reactor components. This work has explored the possibility of reducing H uptake in pressure tube material by incorporating an inhibiting agent into the corrosion environment. Two approaches have been tested, depositing a thin metallic film on the initial oxide surface and adding an inhibiting agent to the solution. The latter approach appears more practical. Screening experiments were conducted in short-term (∝30 day) exposures in high temperature (340 C) aqueous out-reactor environments, simulating the CANDU trademark heat transport coolant with various chemistries. Compounds tested included aluminum acetate, aluminum nitrate, lithium nitrate, rhodium nitrate and yttrium nitrate. Comparison of results from the aluminum nitrate additives and aluminum acetate additives suggests that the nitrate anion is the effective ingredient for H ingress inhibition. The nitrate anion appears to reduce the rate of H ingress regardless of the associated cation. However, each cation appears to affect the rate of corrosion differently. These cations were found to be incorporated in the oxide film. (authors)

Continuing challenges in nuclear air cleaning

International Nuclear Information System (INIS)

Moeller, D.W.

1976-01-01

The safe operation of nuclear facilities is heavily dependent upon the adequate performance of air cleaning systems. Although many problems have been solved, new questions and new challenges continue to arise. These are well illustrated by weaknesses in air cleaning and ventilating systems revealed by the Browns Ferry fire, and the need to develop additional data on the reliability of such systems, particularly under emergency conditions, as revealed by the Reactor Safety Study. Assessments of the degree to which engineered safety features can compensate for deficiencies in nuclear power plant sites continue to challenge those involved in risk/benefit evaluations. Additional challenges are being generated by the air cleaning requirements associated with the commercial development of the liquid metal fast breeder reactor

The ''Nuclear-Karlsruhe'' air-filter system

International Nuclear Information System (INIS)

Berliner, P.; Ohlmeyer, M.; Stotz, W.

1976-01-01

Increasing requirements for exhaust-air filter systems used in nuclear facilities induced the Gesellschaft fuer Kernforschung to develop the ''Nuclear-Karlsruhe'' HEPA filter system. This novel development has profited by experience gained in previous incidents as well as by maitenance and decontamination work performed with different HEPA filter systems. The proved ''Nuclear-Karlsruhe'' system takes equally into account the demands for optimum safety, maximum efficiency and economy, and is distinguished by the following features: (1) The air current is defected by 180 0 in the casing. Deflection causes quite a number of improvements, results in substantial reduction of space requirements, and avoids the dispersion of pollutants to the clean-air side. Besides, the HEPA filter is protected from damage by condensed particles or foreign materials entrained; (2) The ''Nuclear-Karlsruhe'' system allows gas-tight filter replacement. Special replacement collars have been provided at the casing, which allow the tight fastening of replacement bags which are self-locking. (3) In-place testing in the operating condition can be carried out very conveniently because the air is deflected. Minimum leaks in the filter medium or in the filter gasket can be detected by the high-sensitivity visual oil-thread test, which makes leaks distinctly visible as oil mist threads through a transparent front window provided on the clean-air side. The test takes only some minutes and its sensitivity is hardly matched by any other technique. (4) The clamping mechanism is installed outside the casing, i.e. outside the polluted or aggressive media. The contact force is spring-loaded absolutely uniformly to the circular filter gasket. (5) For practical and econmic reasons the filter casings can be locked individually so as to be gas-tight. (6) The entire system is made of stainless or coated steel and metal parts which are corrosion and fire-resistant. (author)

Probabilistic Models and Computational Methods for Chloride Ingress in Concrete

DEFF Research Database (Denmark)

Engelund, S.

Within the last decades it has been recognized that reinforced concrete structures are subject to a number of destructive mechanisms which might affect the structure in such a way that it is not able to fulfil its purpose efficiently. The present report focuses on chloride ingress and chloride...

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.

Characteristic behaviour of Pebble Bed High Temperature Gas-cooled Reactors during water ingress events

International Nuclear Information System (INIS)

Khoza, Samukelisiwe N.; Serfontein, Dawid E.; Reitsma, Frederik

2014-01-01

The presence of water on the tube-side of the steam generators in high temperature gas-cooled reactors (HTGRs) with indirect cycle layouts presents a possibility for a penetration of neutron moderating steam into the core, which may cause a power excursion. This article presents results on the effect of water ingress into the core of the two South African Pebble Bed Modular Reactor design concepts, i.e. the PBMR-200 MW th and the PBMR-400 MW th developed by PBMR SOC Ltd. The VSOP 99/05 suite of codes was used for the simulation of this event. Partial steam vapour pressures were added in stages into the primary circuit in order to investigate the effect of water ingress on reactivity, power profiles and thermal neutron flux profiles. The effects of water ingress into the core are explained by increased neutron moderation, due to the addition of 1 H, which leads to a decrease in resonance capture by 238 U and therefore an increase in the multiplication factor. The more effective moderation of neutrons by definition reduces the fast neutron flux and increases the thermal flux in the core, i.e. leads to a softer spectrum. The more effective moderation also increases the average increase in lethargy between collisions of a neutron with successive fuel kernels, which reduces the probability for neutron capture in the radiative capture resonances of 238 U. The resulting higher resonance escape probability also increases the thermal flux in the core. The softening of the neutron spectrum leads to an increased effective microscopic fission cross section in the fissile isotopes and thus to increased neutron absorption for fission, which reduces the remaining number of neutrons that can diffuse into the reflectors. Therefore water ingress into the core leads to a reduced thermal neutron flux in the reflectors. The power density spatial distribution behaved similarly to the thermal neutron flux in the core. Analysis of possible mechanisms was conducted. The results show that

16th DOE nuclear air cleaning conference: proceedings

International Nuclear Information System (INIS)

First, M.W.

1981-02-01

Major topics discussed during the Sixteenth DOE Nuclear Air Cleaning Conference were: waste treatment, including volume reduction and storage; system and component response to stress and accident conditions; Three Mile Island accident; iodine adsorption; treatment and storage of noble gas: treatment of offgases from chemical processing; aerosol; behavior; containment venting; laboratory and in-place filter-testing methods; and particulate filtration. Volume I of the Proceedings has 49 papers from the following sessions; HEPA filter test methods; noble gas separation; air cleaning system design; containment venting; iodine adsorption; reprocessing offgas cleaning; critical review; filtration; filter testing; and aerosols. Volume II contains 44 papers from the sessions on: nuclear waste treatment; critical review; noble gas treatment; carbon-14 and tritium; air cleaning system response to stress; nuclear standards and safety; round table; open end; and air cleaning technology at Three Mile Island. Abstracts are provided for all of these papers

16th DOE nuclear air cleaning conference: proceedings

International Nuclear Information System (INIS)

First, M.W.

1981-02-01

Major topics discussed during the Sixteenth DOE Nuclear Air Cleaning Conference were: waste treatment, including volume reduction and storage; system and component response to stress and accident conditions; Three Mile Island accident; iodine adsorption; treatment and storage of noble gas; treatment of offgases from chemical processing; aerosol behavior; containment venting; laboratory and in-place filter-testing methods; and particulate filtration. Volume I of the Proceedings has 49 papers from the following sessions: HEPA filter test methods; noble gas separation; air cleaning system design; containment venting; iodine adsorption; reprocessing offgas cleaning; critical review; filtration, filter testing, and aerosols. Volume II contains 44 papers from the sessions on: nuclear waste treatment; critical review; noble gas treatment; carbon-14 and tritium; air cleaning system response to stress; nuclear standards and safety; round table; open end; and air cleaning technology at Three Mile Island. Abstracts are provided for all of these papers

Durability testing of low clinker blends - chloride ingress in similar strength mortar exposed to seawater

DEFF Research Database (Denmark)

Geiker, Mette Rica; De Weerdt, Klaartje; Garzón, Sergio Ferreiro

2017-01-01

Resistance to chloride ingress of ten different binders was investigated. Most of the binders were prepared with 35% substitution of a new clinker by limestone filler, calcined clay, burnt shale and/or siliceous fly ash. Mortar samples with similar design compressive strength after 90 days were e...... exposed to artificial sea-water for 270 days. The results indicate that the use of alternative binders may lead to up to around 15% reduction in CO2 emission without compromising 90 days compressive strength and resistance to chloride ingress in marine exposure....

Deposition of RuO 4 on various surfaces in a nuclear reactor containment

Science.gov (United States)

Holm, Joachim; Glänneskog, Henrik; Ekberg, Christian

2009-07-01

During a severe nuclear reactor accident with air ingress, ruthenium can be released from the nuclear fuel in the form of ruthenium tetroxide. Hence, it is important to investigate how the reactor containment is able to reduce the source term of ruthenium. The aim of this work was to investigate the deposition of gaseous ruthenium tetroxide on aluminium, copper and zinc, which all appear in relatively large amounts in reactor containment. The experiments show that ruthenium tetroxide is deposited on all the metal surfaces, especially on the copper and zinc surfaces. A large deposition of ruthenium tetroxide also appeared on the relatively inert glass surfaces in the experimental set-ups. The analyses of the different surfaces, with several analytical methods, showed that the form of deposited ruthenium was mainly ruthenium dioxide.

Oxygen ingress study of 3D printed gaseous radiation detector enclosures

Energy Technology Data Exchange (ETDEWEB)

Steer, Christopher A.; Durose, Aaron [AWE, Alderrnaston, Reading, Berkshire, RG7 4PR (United Kingdom)

2015-07-01

As part of our ongoing studies into the potential application of 3D printing techniques to gaseous radiation detectors, we have studied the ability of 3D printed enclosures to resist environmental oxygen ingress. A set of cuboid and hexagonal prism shaped enclosures with wall thicknesses of 4 mm, 6 mm, 8 mm and 10 mm were designed and printed in nylon using a EOSINT P 730 Selective Laser Sintering 3D printer system These test enclosures provide a comparison of different environmental gas ingress for different 3D printing techniques. The rate of change of oxygen concentration was found to be linear, decreasing as the wall thickness increases. It was also found that the hexagonal prism geometry produced a lower rate of change of oxygen concentration compared with the cuboid shaped enclosures. Possible reasons as to why these results were obtained are discussed The implications for the this study for deployable systems are also discussed (authors)

Oxygen ingress study of 3D printed gaseous radiation detector enclosures

International Nuclear Information System (INIS)

Steer, Christopher A.; Durose, Aaron

2015-01-01

As part of our ongoing studies into the potential application of 3D printing techniques to gaseous radiation detectors, we have studied the ability of 3D printed enclosures to resist environmental oxygen ingress. A set of cuboid and hexagonal prism shaped enclosures with wall thicknesses of 4 mm, 6 mm, 8 mm and 10 mm were designed and printed in nylon using a EOSINT P 730 Selective Laser Sintering 3D printer system These test enclosures provide a comparison of different environmental gas ingress for different 3D printing techniques. The rate of change of oxygen concentration was found to be linear, decreasing as the wall thickness increases. It was also found that the hexagonal prism geometry produced a lower rate of change of oxygen concentration compared with the cuboid shaped enclosures. Possible reasons as to why these results were obtained are discussed The implications for the this study for deployable systems are also discussed (authors)

Testing and operation of nuclear air-cleaning systems in Qinshan NPP

International Nuclear Information System (INIS)

Yang Lin

1993-01-01

The components of nuclear air-cleaning system, system function, operational mode and the performance of cleaning components in Qinshan Nuclear Power Plant are described. The items, purpose, methods and results of in-place testing after the installation are also described in detail. The in-place testing verifies that nuclear air-cleaning systems in Qinshan Nuclear Power Plant are reliable and high effective. It also describes the points of the operational management. It is shown that the good operational management is the key which developed prescription function of nuclear air-cleaning systems. At present, Qinshan Nuclear Power Plant will be in full power, the normal operation of the system is satisfied with the demand of safe operation in Qinshan Nuclear Power Company

Deposition of RuO{sub 4} on various surfaces in a nuclear reactor containment

Energy Technology Data Exchange (ETDEWEB)

Holm, Joachim, E-mail: joachim.holm@chalmers.s [Department of Nuclear Chemistry, Chalmers University of Technology, Se-412 96 Gothenburg (Sweden); Glaenneskog, Henrik [Ringhals AB, SE-430 22, Vaeroebacka (Sweden); Ekberg, Christian [Department of Nuclear Chemistry, Chalmers University of Technology, Se-412 96 Gothenburg (Sweden)

2009-07-01

During a severe nuclear reactor accident with air ingress, ruthenium can be released from the nuclear fuel in the form of ruthenium tetroxide. Hence, it is important to investigate how the reactor containment is able to reduce the source term of ruthenium. The aim of this work was to investigate the deposition of gaseous ruthenium tetroxide on aluminium, copper and zinc, which all appear in relatively large amounts in reactor containment. The experiments show that ruthenium tetroxide is deposited on all the metal surfaces, especially on the copper and zinc surfaces. A large deposition of ruthenium tetroxide also appeared on the relatively inert glass surfaces in the experimental set-ups. The analyses of the different surfaces, with several analytical methods, showed that the form of deposited ruthenium was mainly ruthenium dioxide.

Experience of air transport of nuclear fuel material as type A package

International Nuclear Information System (INIS)

Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

2004-01-01

Special law on nuclear disaster countermeasures (hereafter called as to nuclear disaster countermeasures low) that is domestic law for dealing with measures for nuclear disaster, was enforced in June, 2000. Therefore, nuclear enterprise was obliged to report accidents as required by nuclear disaster countermeasures law, besides meeting the technical requirement of existent transport regulation. For overseas procurement of plutonium reference materials that are needed for material accountability, A Type package must be transported by air. Therefore, concept of air transport of nuclear fuel materials according to the nuclear disaster countermeasures law was discussed, and the manual including measures against accident in air transport was prepared for the oversea procurement. In this presentation, the concept of air transport of A Type package containing nuclear fuel materials according to the nuclear disaster countermeasures law, and the experience of a transportation of plutonium solution from France are shown. (author)

Guidance for air sampling at nuclear facilities

International Nuclear Information System (INIS)

Breslin, A.J.

1976-11-01

The principal uses of air sampling at nuclear facilities are to monitor general levels of radioactive air contamination, identify sources of air contamination, and evaluate the effectiveness of contaminant control equipment, determine exposures of individual workers, and provide automatic warning of hazardous concentrations of radioactivity. These applications of air sampling are discussed with respect to standards of occupational exposure, instrumentation, sample analysis, sampling protocol, and statistical treatment of concentration data. Emphasis is given to the influence of spacial and temporal variations of radionuclide concentration on the location, duration, and frequency of air sampling

Air and gas cleaning technology for nuclear applications

International Nuclear Information System (INIS)

First, M.W.

1986-01-01

All large-scale uses of radioactive materials require rigid control of off-gases and generated aerosols. Nuclear air and gas cleaning technology has answered the need from the days of the Manhattan Project to the present with a variety of devices. The one with the longest and most noteworthy service is the HEPA (high efficiency particulate air) filter that originally was referred to as an absolute filter in recognition of its extraordinary particle retention characteristics. Activated-charcoal adsorbers have been employed worldwide for retention of volatile radioiodine in molecular and combined forms and, less frequently, for retention of radioactive noble gases. HEPA filters and activated -charcoal adsorbers are often used with auxiliary devices that serve to extend their effective service life or significantly improve collection efficiency under unfavorable operating conditions. Use of both air cleaning devices and their auxiliaries figure prominently in atomic energy, disposal of high- and low-level nuclear wastes, and in the production of fissile materials. The peaceful uses of nuclear energy would be impossible without these, or equivalent, air- and gas-cleaning devices

Moisture ingress into electronics enclosures under isothermal conditions

DEFF Research Database (Denmark)

Staliulionis, Zygimantas; Jabbaribehnam, Mirmasoud; Hattel, Jesper Henri

2016-01-01

loads are still not understood well by design engineers, therefore this field has become one of the bottlenecks in the electronics system design. The objective of this paper is to model moisture ingress into an electronics enclosure under isothermal conditions. The moisture diffusion model is based......The number of electronics used in outdoor environment is constantly growing. The humidity causes about 19 % of all electronics failures and, especially, moisture increases these problems due to the ongoing process of miniaturization and lower power consumption of electronic components. Moisture...

Air-conditioning and ventilation systems and components of nuclear facilities

International Nuclear Information System (INIS)

2006-01-01

The Guide defines the requirements for the design, implementation and operation of the air-conditioning and ventilation systems of nuclear facilities belonging to safety classes 3 and 4, and for the related documents to be submitted to STUK (Radiation and Nuclear Safety Authority, Finland). Furthermore, the Guide describes the inspections of air-conditioning and ventilation systems to be conducted by STUK during construction and operation of the facilities. As far as systems and components belonging to safety class 2 are concerned, STUK sets additional requirements case by case. In general, air-conditioning systems refer to systems designed to manage the indoor air cleanness, temperature, humidity and movement. In some rooms of a nuclear power plant, ventilation systems are also used to prevent radioactive materials from spreading outside the rooms. Guide YVL1.0 defines the safety principles concerning the air-conditioning and ventilation of nuclear power plants. Guide YVL2.0 gives the requirements for the design of nuclear power plant systems. In addition, YVLGuide groups 3, 4, 5 and 7 deal with the requirements for air-conditioning and ventilation systems with regard to the mechanical equipment, fire prevention, electrical systems, instrumentation and control technology, and the restriction of releases. The rules and regulations issued by the Ministry of the Environment and the Ministry of the Interior (RakMK, the Finnish building code) concerning the design and operation of air-conditioning and ventilation systems and the related fire protection design bases also apply to nuclear facilities. Exhaust gas treatment systems, condenser vacuum systems of boiling water reactor plants and leak collection systems are excluded from the scope of this Guide

Chloride ingress in cracked concrete : A laser induced breakdown spectroscopy (LIBS) study

NARCIS (Netherlands)

Savija, B.; Schlangen, E.; Pacheco Farias, J.; Millar, S.; Eichler, T.; Wilsch, G.

2014-01-01

racks are always present in reinforced concrete structures. In the presented research, influence of mechanical cracks on chloride ingress is studied. A compact reinforced concrete specimen was designed, mimicking the cracking behaviour of beam elements. Cracks of different widths were induced by

Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

Energy Technology Data Exchange (ETDEWEB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1995-02-01

The report contains the papers presented at the 23rd DOE/NRC Nuclear Air Cleaning Conference and the associated discussions. Major topics are: (1) nuclear air cleaning codes, (2) nuclear waste, (3) filters and filtration, (4) effluent stack monitoring, (5) gas processing, (6) adsorption, (7) air treatment systems, (8) source terms and accident analysis, and (9) fuel reprocessing. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Simulation of lumbar and neck angle flexion while ingress of paratransit (angkot in Indonesia as a preliminary design study

Directory of Open Access Journals (Sweden)

Yukhi Mustaqim Kusuma Sya’bana

2017-12-01

Full Text Available This is the preliminary finding of a study to simulate lumbar and neck flexion while ingress to the paratransit. The result of simulation will determine design aspect criteria as a preliminary step before ideation and implementation design steps. Biomechanics of Bodies (BoB is software that used to represent passenger task during paratransit ingress simulation, with skeleton model that used is height 165 cm and weight 65 kg. Environment to represent this simulation is measured Suzuki Carry SS 2013 as a private car that has been modified into a public transportation in accordance with the Indonesian government road-worthy test. Due to the low height of the entrance and the high ground clearance, lumbar and neck joint angle was a focus of this ingress simulation. The peak angle at the neck joint is 40° when 2 s skeleton nod in the door limitation ingress and lumbar flexion is 70° when 5 s skeleton is walking while bend over that will increase the load on that area. Based on biomechanical simulation approach, we may suggest the dimension of public transportation design framework developments, especially paratransit.

Effect of steam corrosion on core post strength loss: I. Low, chronic steam ingress rates

International Nuclear Information System (INIS)

Wichner, R.P.

1976-10-01

The purpose of the study was to assess the effect of chronic, low levels of steam ingress into the primary system of the HTGR on the corrosion, and consequent strength loss of the core support posts. The assessment proceeded through the following three steps: (1) The impurity composition in the primary system was estimated as a function of a range of steady ingress rates of from 0.001 to 1.0 g/sec, both by means of an analysis of the Dragon steam ingress experiment and a computer code, TIMOX, which treats the primary system as a well-mixed pot. (2) The core post burnoffs which result from 40-year exposures to these determined impurity atmospheres were then estimated using a corrosion rate expression derived from published ATJ-graphite corrosion rate data. Burnoffs were determined for both the core posts at the nominal and the maximum sustained temperature, estimated to be 90 0 C above nominal. (3) The final step involved assessment of the degree of strength loss resulting from the estimated burnoffs. An empirical equation was developed for this purpose which compares reasonably well with strength loss data for a number of different graphites and specimen geometries

Radionuclide characterization of environmental air around nuclear facilities

International Nuclear Information System (INIS)

Gede Sutresna Wijaya; Anung Muharini

2015-01-01

Air is an important environmental component in human life. Presence of air pollutants or contaminants will have a negative impact on human health. According to the existence of a nuclear facility in Yogyakarta, the characterization of radionuclides in the air is absolutely necessary to ensure the safety of people and the environment and also to supervise the safe operation of the facility. In this research the characterization of radionuclides in the air was carried through the air sampling by using High Volume Air Sampler equipped with filter TFA 2133, followed by analysis using combination of a gamma and alpha spectrometers. The concentration of radioactivity in the air fluctuates depending on the time and duration of sampling. Characterization of gamma emitting radionuclides in the air is dominated by radon progeny radionuclides such as 214 Pb, 214 Bi with activity 20.09 ± 1.23 until 32.91 ± 4.87 Bq/m 3 and 31.22 ± 1.76 until 44.25 ± 4.91 Bq/m 3 . Alpha emitter radionuclide was dominated by 214 Po (7.69 MeV) which is also radon progeny and a primordial radionuclides. It can be concluded that the presence of radionuclides in the environmental air not as a product resulting from the operation of nuclear facilities in Yogyakarta. (author)

Testing of nuclear air-cleaning systems

International Nuclear Information System (INIS)

Anon.

1975-01-01

A standard is presented which describes methods for field-testing nuclear power plant air cleaning systems. Included are specifications for visual inspection; duct and housing leak test; mounting frame pressure leak test; airflow capacity, distribution, and residence time tests; air-aerosol mixing uniformity test; in place leak test of HEPA filter banks; multiple sampling technique; in-place leak test of adsorber stage; laboratory testing of adsorbent; and duct heater performance test

The Air Blast Wave from a Nuclear Explosion

Science.gov (United States)

Reines, Frederick

The sudden, large scale release of energy in the explosion of a nuclear bomb in air gives rise, in addition to nuclear emanations such as neutrons and gamma rays, to an extremely hot, rapidly expanding mass of air.** The rapidly expanding air mass has an initial temperature in the vicinity of a few hundred thousand degrees and for this reason it glows in its early stages with an intensity of many suns. It is important that the energy density in this initial "ball of fire" is of the order of 3 × 103 times that found in a detonating piece of TNT and hence that the initial stages of the large scale air motion produced by a nuclear explosion has no counterpart in an ordinary. H. E. explosion. Further, the relatively low temperatures ˜2,000°C associated with the initial stages of an H. E. detonation implies that the thermal radiation which it emits is a relatively insignificant fraction of the total energy involves. This point is made more striking when it is remembered that the thermal energy emitted by a hot object varies directly with the temperature in the Rayleigh Jeans region appropriate to the present discussion. The expansion of the air mass heated by the nuclear reaction produces, in qualitatively the same manner as in an H.E. explosion or the bursting of a high pressure balloon, an intense sharp pressure pulse, a shock wave, in the atmosphere. As the pressure pulse spreads outward it weakens due to the combined effects of divergence and the thermodynamically irreversible nature of the shock wave. The air comprising such a pressure pulse or blast wave moves first radially outward and then back towards the center as the blast wave passes. Since a permanent outward displacement of an infinite mass of air would require unlimited energy, the net outward displacement of the air distant from an explosion must approach zero with increasing distance. As the distance from the explosion is diminished the net outward displacement due to irreversible shock heating of

Vision-Aided Autonomous Landing and Ingress of Micro Aerial Vehicles

Science.gov (United States)

Brockers, Roland; Ma, Jeremy C.; Matthies, Larry H.; Bouffard, Patrick

2012-01-01

Micro aerial vehicles have limited sensor suites and computational power. For reconnaissance tasks and to conserve energy, these systems need the ability to autonomously land at vantage points or enter buildings (ingress). But for autonomous navigation, information is needed to identify and guide the vehicle to the target. Vision algorithms can provide egomotion estimation and target detection using input from cameras that are easy to include in miniature systems.

Applied research on air pollution using nuclear-related analytical techniques

International Nuclear Information System (INIS)

1994-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which will run from 1992-1996, and will build upon the experience gained by the Agency from the laboratory support that it has been providing for several years to BAPMoN - the Background Air Pollution Monitoring Network programme organized under the auspices of the World Meterological Organization. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XFR, and PIXE for the analysis of toxic and other trace elements in suspended particulate matter (including air filter samples), rainwater and fog-water samples, and in biological indicators of air pollution (e.g. lichens and mosses). The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for practically-oriented research and monitoring studies on air pollution ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural areas). This document reports the discussions held during the first Research Co-ordination Meeting (RCM) for the CRP which took place at the IAEA Headquarters in Vienna. Refs, figs and tabs

Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8

Energy Technology Data Exchange (ETDEWEB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1991-02-01

Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

Mapping air pollution. Application of nuclear techniques

International Nuclear Information System (INIS)

Parr, R.M.; Stone, S.F.; Zeisler, R.

1996-01-01

Nuclear techniques have important applications in the study of air pollution and many of its components. However, it is in the study of airborne particulate matter (APM) that nuclear analytical techniques find many of their most important applications. This article focuses on those applications, and on the work of the IAEA in this important field of study. 2 figs

Hypothetical air ingress scenarios in advanced modular high temperature gas cooled reactors

International Nuclear Information System (INIS)

Kroeger, P.G.

1988-01-01

Considering an extremely hypothetical scenario of complete cross duct failure and unlimited air supply into the reactor vessel of a modular high temperature gas cooled ractor, it is found that the potential air inflow remains limited due to the high friction pressure drop through the active core. All incoming air will be oxidized to CO and some local external burning would be temporarily possible in such a scenario. The accident would have to continue with unlimited air supply for hundreds of hours before the core structural integrity would be jeopardized

Proceedings of the 21st DOE/NRC nuclear air cleaning conference

International Nuclear Information System (INIS)

First, M.W.

1991-02-01

The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers

Monitoring Ingress of Moisture in Structural Concrete Using a Novel Optical-Based Sensor Approach

International Nuclear Information System (INIS)

Yeo, T L; Cox, M A C; Boswell, L F; Sun, T; Grattan, K T V

2006-01-01

The detection of moisture ingress in concrete is important for structural monitoring and in this work is realised by monitoring the shift in the characteristic wavelength of a fibre Bragg grating-based sensor. The sensor relies upon a moisture-sensitive polymer layer deposited on the fibre Bragg grating (FBG) and the strain induced on it as a result of polymer swelling is monitored. Moisture ingress experiments were carried out using two such optical fibre sensors, placed at varying distances from the edge of the face of standard concrete cubes to the inner part of the concrete sample and subjected to water at a constant temperature. Information on the properties of different types of concrete and thus potentially on the migration of dissolved salts and their effect on reinforcement bars within concrete can be obtained

An introduction to the design, commissioning and operation of nuclear air cleaning systems for Qinshan Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Xinliang Chen; Jiangang Qu; Minqi Shi [Shanghai Nuclear Engineering Research and Design Institute (China)] [and others

1995-02-01

This paper introduces the design evolution, system schemes and design and construction of main nuclear air cleaning components such as HEPA filter, charcoal adsorber and concrete housing etc. for Qinshan 300MW PWR Nuclear Power Plant (QNPP), the first indigenously designed and constructed nuclear power plant in China. The field test results and in-service test results, since the air cleaning systems were put into operation 18 months ago, are presented and evaluated. These results demonstrate that the design and construction of the air cleaning systems and equipment manufacturing for QNPP are successful and the American codes and standards invoked in design, construction and testing of nuclear air cleaning systems for QNPP are applicable in China. The paper explains that the leakage rate of concrete air cleaning housings can also be assured if sealing measures are taken properly and embedded parts are designed carefully in the penetration areas of the housing and that the uniformity of the airflow distribution upstream the HEPA filters can be achieved generally no matter how inlet and outlet ducts of air cleaning unit are arranged.

A software tool for evaluation of hydrogen ingress in CANDU pressure tubes

International Nuclear Information System (INIS)

Mihalache, Maria; Vasile, Radu; Deaconu, Mariea

2009-01-01

The prediction of hydrogen isotopes concentration into the body and in the rolled joints of operating pressure tubes as a function of reactor hot hours is very important in many fitness-for-service assessments and end of life estimates. The rolled joints are high stress zones with potential for delayed hydride cracking. Predictive models for assessing the long-term deuterium ingress in both body and rolled joint of the pressure tubes have been implemented in a software tool, ROHID, developed in INR-Pitesti. ROHID is a PC-based Windows application with a user-friendly interface that predicts the equivalent hydrogen ingress for Zr-2.5Nb pressure tubes. It uses colour-coded reactor core maps to display the predicted deuterium concentration as a function of time for selected axial locations. Plots of deuterium versus axial location and time for individual pressure tubes are also available. Also, the software tool can predict the exceeding of hydrogen terminal solid solubility (HTSS) from hydrides during precipitation and dissolving processes as a function of time and axial location. (authors)

Evaluation of ATP measurements to detect microbial ingress by wastewater and surface water in drinking water.

Science.gov (United States)

Vang, Óluva K; Corfitzen, Charlotte B; Smith, Christian; Albrechtsen, Hans-Jørgen

2014-11-01

Fast and reliable methods are required for monitoring of microbial drinking water quality in order to protect public health. Adenosine triphosphate (ATP) was investigated as a potential real-time parameter for detecting microbial ingress in drinking water contaminated with wastewater or surface water. To investigate the ability of the ATP assay in detecting different contamination types, the contaminant was diluted with non-chlorinated drinking water. Wastewater, diluted at 10(4) in drinking water, was detected with the ATP assay, as well as 10(2) to 10(3) times diluted surface water. To improve the performance of the ATP assay in detecting microbial ingress in drinking water, different approaches were investigated, i.e. quantifying microbial ATP or applying reagents of different sensitivities to reduce measurement variations; however, none of these approaches contributed significantly in this respect. Compared to traditional microbiological methods, the ATP assay could detect wastewater and surface water in drinking water to a higher degree than total direct counts (TDCs), while both heterotrophic plate counts (HPC 22 °C and HPC 37 °C) and Colilert-18 (Escherichia coli and coliforms) were more sensitive than the ATP measurements, though with much longer response times. Continuous sampling combined with ATP measurements displays definite monitoring potential for microbial drinking water quality, since microbial ingress in drinking water can be detected in real-time with ATP measurements. The ability of the ATP assay to detect microbial ingress is influenced by both the ATP load from the contaminant itself and the ATP concentration in the specific drinking water. Consequently, a low ATP concentration of the specific drinking water facilitates a better detection of a potential contamination of the water supply with the ATP assay. Copyright © 2014 Elsevier Ltd. All rights reserved.

Nuclear air cleaning programs in progress in France

International Nuclear Information System (INIS)

Mulcey, P.

1991-01-01

A short presentation is given of the nuclear air cleaning programs in progress in France with respect to pressurized water reactors, fuel reprocessing plants, radioactive waste management facilities, and the dismantling of nuclear facilities. The effects of fires in rooms and ventilation ducts in all nuclear facilities is being studied and computer simulation codes are being developed. A brief review of filter development and filter testing is also presented

Reducing the ingress of urban noise through natural ventilation openings.

Science.gov (United States)

Oldham, D J; de Salis, M H; Sharples, S

2004-01-01

For buildings in busy urban areas affected by high levels of road traffic noise the potential to use natural ventilation can be limited by excessive noise entering through ventilation openings. This paper is concerned with techniques to reduce noise ingress into naturally ventilated buildings while minimizing airflow path resistance. A combined experimental and theoretical approach to the interaction of airflow and sound transmission through ventilators for natural ventilation applications is described. A key element of the investigation has been the development of testing facilities capable of measuring the airflow and sound transmission losses for a range of ventilation noise control strategies. It is demonstrated that a combination of sound reduction mechanisms -- one covering low frequency sound and another covering high frequency sound -- is required to attenuate effectively noise from typical urban sources. A method is proposed for quantifying the acoustic performance of different strategies to enable comparisons and informed decisions to be made leading to the possibility of a design methodology for optimizing the ventilation and acoustic performance of different strategies. The need for employing techniques for combating low frequency sound in tandem with techniques for reducing high frequency sound in reducing the ingress of noise from urban sources such as road traffic to acceptable levels is demonstrated. A technique is proposed for enabling the acoustic and airflow performance of apertures for natural ventilation systems to be designed simultaneously.

Influence of temporal resolution and processing of exposure data on modeling of chloride ingress and reinforcement corrosion in concrete

DEFF Research Database (Denmark)

Flint, Madeleine; Michel, Alexander; Billington, Sarah L.

2014-01-01

a numerical heat and mass transport model that includes full coupling of heat, moisture and ion transport. Heat, moisture, and chloride concentration distributions were passed to a simplified reinforcement corrosion initiation and propagation model. The numerical study indicates that processing and temporal...... resolution of the exposure data has a considerable impact on long-term hygrothermal distribution, chloride ingress, and reinforcement section loss results. Use of time-averaged exposure data in the heat and mass transport model reduces the rate of chloride ingress in concrete and affects prediction...

The Evolution of Air and Nuclear Doctrine: The Theories that Shaped SIOP-62

Science.gov (United States)

2016-06-01

STUDIES AIR UNIVERSITY MAXWELL AIR FORCE BASE, ALABAMA JUNE 2016 DISTRIBUTION A. Approved for public release: distribution unlimited ii...recommendations including, in April 1956, advanced authorization to Air Defense Command to use nuclear-tipped Nike -Hercules surface-to-air missiles to...The Sources of Military Doctrine, 14-15. 58 nuclear strike.101 In response, the Secretary of Defense ordered deployment of Nike -Hercules

Operating experience of a sodium rig following the ingress of oil

Energy Technology Data Exchange (ETDEWEB)

Bell, A C; Mehew, R D; Robertson, C M [UKAEA, Dounreay, Thurso, Caithness, Scotland (United Kingdom)

1980-05-01

The experience of operating the Small Water Leak Rig at Dounreay in the two years following the ingress into the sodium of silicone oil from the pump is reported. The carbon penetration into the rig pipework has been monitored and has been found to agree with a diffusion model. The predictions based on this model have enabled an operating strategy to be determined to allow continued operation of the rig. (author)

Operating experience of a sodium rig following the ingress of oil

International Nuclear Information System (INIS)

Bell, A.C.; Mehew, R.D.; Robertson, C.M.

1980-01-01

The experience of operating the Small Water Leak Rig at Dounreay in the two years following the ingress into the sodium of silicone oil from the pump is reported. The carbon penetration into the rig pipework has been monitored and has been found to agree with a diffusion model. The predictions based on this model have enabled an operating strategy to be determined to allow continued operation of the rig. (author)

Continuum-based DFN-consistent simulations of oxygen ingress in fractured crystalline rocks

Science.gov (United States)

Trinchero, P.; Puigdomenech, I.; Molinero, J.; Ebrahimi, H.; Gylling, B.; Svensson, U.; Bosbach, D.; Deissmann, G.

2016-12-01

The potential transient infiltration of oxygenated glacial meltwater into initially anoxic and reducing fractured crystalline rocks during glaciation events is an issue of concern for some of the prospected deep geological repositories for spent nuclear fuel. Here, this problem is assessed using reactive transport calculations. First, a novel parameterisation procedure is presented, where flow, transport and geochemical parameters (i.e. hydraulic conductivity, effective/kinetic porosity, and mineral specific surface and abundance) are defined on a finite volume numerical grid based on the (spatially varying) properties of an underlying Discrete Fracture Network (DFN). Second, using this approach, a realistic reactive transport model of Forsmark, i.e. the selected site for the proposed Swedish spent nuclear fuel repository, is implemented. The model consists of more than 70 million geochemical transport degrees of freedom and simulates the ingress of oxygen-rich water from the recharge area of the domain and its depletion due to reactions with the Fe(II) mineral chlorite. Third, the calculations are solved in the supercomputer JUQUEEN of the Jülich Supercomputing Centre. The results of the simulations show that oxygen infiltrates relatively quickly along fractures and deformation zones until a steady state profile is reached, where geochemical reactions counterbalance advective transport processes. Interestingly, most of the iron-bearing minerals are consumed in the highly conductive zones, where larger mineral surfaces are available for reactions. An analysis based on mineral mass balance shows that the considered rock medium has enough capacity to buffer oxygen infiltration for a long period of time (i.e. some thousand years).

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

Energy Technology Data Exchange (ETDEWEB)

K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin

2010-07-01

Romania safely air shipped 23.7 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel from the VVR S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world’s first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment.

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

International Nuclear Information System (INIS)

Allen, K.J.; Bolshinsky, I.; Biro, L.L.; Budu, M.E.; Zamfir, N.V.; Dragusin, M.

2010-01-01

Romania safely air shipped 23.7 kilograms of Russian-origin highly enriched uranium (HEU) spent nuclear fuel from the VVR-S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world's first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3. country under the RRRFR program and the 14. country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment. (authors)

Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

International Nuclear Information System (INIS)

First, M.W.

1997-08-01

This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

Energy Technology Data Exchange (ETDEWEB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1997-08-01

This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Sample and injection manifolds used to in-place test of nuclear air-cleaning system

International Nuclear Information System (INIS)

Qiu Dangui; Li Xinzhi; Hou Jianrong; Qiao Taifei; Wu Tao; Zhang Jirong; Han Lihong

2012-01-01

Objective: According to the regulations of nuclear safety rules and related standards, in-place test of the nuclear air-cleaning systems should be carried out before and during operation of the nuclear facilities, which ensure them to be in good condition. In some special conditions, the use of sample and injection manifolds is required to make the test tracer and ventilating duct air fully mixed, so as to get the on-spot typical sample. Methods: This paper introduces the technology and application of the sample and injection manifolds in nuclear air-cleaning system. Results: Multi point injection and multi point sampling technology as an effective experimental method, has been used in a of domestic and international nuclear facilities. Conclusion: The technology solved the problem of uniformly of on-spot injection and sampling,which plays an important role in objectively evaluating the function of nuclear air-cleaning system. (authors)

Ventilation and air-conditioning system for PWR nuclear power plant

International Nuclear Information System (INIS)

Ohmoto, Kenji

1987-01-01

This report outlines the ventilation and air conditioning facilities for PWR nuclear power plant as well as design re-evaluation and optimization of ventilation and air-conditioning. The primary PWR installations are generally housed in the nuclear reactor building, auxiliary buildings and control building, which are equipped with their own ventilation and air-conditioning systems to serve for their specific purposes. A ventilation/air-conditioning system should be able to work effectively not only for maintaining the ordinary reactor operation but also for controlling the environmental temperature in the event of an accident. Designing of a ventilation/air-conditioning system relied on empirical data in the past, but currently it is performed based on information obtained from various analyses to optimize the system configuration and ventilation capacity. Design re-evaluation of ventilation/air-conditioning systems are conducted widely in various areas, aiming at the integration of safety systems, optimum combination of air-cooling and water-cooling systems, and optimization of the ventilation rate for controlling the concentrations of radioactive substances in the atmosphere in the facilities. It is pointed out that performance evaluation of ventilation/air-conditioning systems, which has been conducted rather macroscopically, should be carried out more in detal in the future to determine optimum air streams and temperature distribution. (Nogami, K.)

Pressurizing Behavior on Ingress of Coolant into Pebble Bed of Blanket of Fusion DEMO Reactor

International Nuclear Information System (INIS)

Daigo Tsuru; Mikio Enoeda; Masato Akiba

2006-01-01

Solid breeder blankets are being developed as candidate blankets for the Fusion DEMO reactor in Japan. JAEA is performing the development of the water cooled and helium cooled solid breeder blankets. The blanket utilizes ceramic breeder pebbles and multiplier pebbles beds cooled by high pressure water or high pressure helium in the cooling tubes placed in the blanket box structure. In the development of the blanket, it is very important to incorporate the safety technology as well as the performance improvement on tritium production and energy conversion. In the safety design and technology, coolant ingress in the blanket box structure is one of the most important events as the initiators. Especially the thermal hydraulics in the pebble bed in the case of the high pressure coolant ingress is very important to evaluate the pressure propagation and coolant flow behavior. This paper presents the preliminary results of the pressure loss characteristics by the coolant ingress in the pebble bed. Experiments have been performed by using alumina pebble bed (4 litter maximum volume of the pebble bed) and nitrogen gas to simulate the helium coolant ingress into breeder and multiplier pebble beds. Reservoir tank of 10 liter is filled with 1.0 MPa nitrogen. The nitrogen gas is released at the bottom part of the alumina pebble bed whose upper part is open to the atmosphere. The pressure change in the pebble bed is measured to identify the pressure loss. The measured values are compared with the predicted values by Ergun's equation, which is the correlation equation on pressure loss of the flow through porous medium. By the results of the experiments with no constraint on the alumina pebble bed, it was clarified that the measured value agreed in the lower flow rate. However, in the higher flow rate where the pressure loss is high, the measured value is about half of the predicted value. The differences between the measured values and the predicted values will be discussed from

Oxygen Selective Membranes for Li-Air (O₂ Batteries

Directory of Open Access Journals (Sweden)

Mark Salomon

2012-05-01

Full Text Available Lithium-air (Li-air batteries have a much higher theoretical energy density than conventional lithium batteries and other metal air batteries, so they are being developed for applications that require long life. Water vapor from air must be prevented from corroding the lithium (Li metal negative electrode during discharge under ambient conditions, i.e., in humid air. One method of protecting the Li metal from corrosion is to use an oxygen selective membrane (OSM that allows oxygen into the cell while stopping or slowing the ingress of water vapor. The desired properties and some potential materials for OSMs for Li-air batteries are discussed and the literature is reviewed.

Magnitude and reactivity consequences of moisture ingress into the modular High-Temperature Gas-Cooled Reactor core

International Nuclear Information System (INIS)

Smith, O.L.

1992-12-01

Inadvertent admission of moisture into the primary system of a modular high-temperature gas-cooled reactor has been identified in US Department of Energy-sponsored studies as an important safety concern. The work described here develops an analytical methodology to quantify the pressure and reactivity consequences of steam-generator tube rupture and other moisture-ingress-related incidents. Important neutronic and thermohydraulic processes are coupled with reactivity feedback and safety and control system responses. The rate and magnitude of steam buildup are found to be dominated by major system features such as break size compared with safety valve capacity and reliability and less sensitive to factors such as heat transfer coefficients. The results indicate that ingress transients progress at a slower pace than previously predicted by bounding analyses, with milder power overshoots and more time for operator or automatic corrective actions

Oxidation Resistant Graphite Studies

Energy Technology Data Exchange (ETDEWEB)

W. Windes; R. Smith

2014-07-01

The Very High Temperature Reactor (VHTR) Graphite Research and Development Program is investigating doped nuclear graphite grades exhibiting oxidation resistance. During a oxygen ingress accident the oxidation rates of the high temperature graphite core region would be extremely high resulting in significant structural damage to the core. Reducing the oxidation rate of the graphite core material would reduce the structural effects and keep the core integrity intact during any air-ingress accident. Oxidation testing of graphite doped with oxidation resistant material is being conducted to determine the extent of oxidation rate reduction. Nuclear grade graphite doped with varying levels of Boron-Carbide (B4C) was oxidized in air at nominal 740°C at 10/90% (air/He) and 100% air. The oxidation rates of the boronated and unboronated graphite grade were compared. With increasing boron-carbide content (up to 6 vol%) the oxidation rate was observed to have a 20 fold reduction from unboronated graphite. Visual inspection and uniformity of oxidation across the surface of the specimens were conducted. Future work to determine the remaining mechanical strength as well as graphite grades with SiC doped material are discussed.

Aerosol challenges to air cleaning systems during severe accidents in nuclear plants

International Nuclear Information System (INIS)

Gieseke, J.A.

1985-01-01

A variety of air cleaning systems may be operating in nuclear power plants and under severe accident conditions, these systems may be treating airborne concentrations of aerosols which are very high. Predictions of airborne aerosol concentrations in nuclear power plant containments under severe accident conditions are reviewed to provide a basis for evaluating the potential effects on the air cleaning systems. The air cleaning systems include filters, absorber beds, sprays, water pools, ice beds, and condensers. Not all of these were intended to operate as air cleaners but will in fact be good aerosol collectors. Knowledge of expected airborne concentrations will allow better evaluation of system performances

Investigations on accidents with massive water ingress exemplified by the pebble bed reactor PNP-500

International Nuclear Information System (INIS)

Moormann, R.

1986-01-01

A computer code is used for analyses of massive water ingress accidents in the High-Temperature Gas Cooled Reactor concept PNP-500 with pebble bed core. The analyses are mainly focussed on graphite corrosion processes. For the investigated accidents a correct reactor shut down in assumed. The mass of water ingressing into the primary circuit is varied between 1000 and 7500 kg (i.e., up to hypothetical values). The dependence of accident consequences on parameters such as intensity and starting time of the afterheat removal system or kinetic values of the chemical processes is examined. The results show that even under pessimistic assumptions the extent of the graphite corrosion is relatively low; significant damaging of fuel elements or graphite components does not occur. A primary circuit depressurization, combined with local burning of water gas, would probably not affect the fission product retention potential of the (gastight) containment. Summing up, the risk caused by these accidents remains small. (orig.) [de

Nuclear air cleaning activities in Germany

International Nuclear Information System (INIS)

Wilhelm, J.

1991-01-01

The discussion is limited to nuclear air cleaning activities in the Federal Republic of Germany. Work is underway on containment venting with regard to filtration based on a combination of stainless steel roughing and fine filters with a decontamination factor similar to or better than that achieved with high-efficiency particulate air filters. The main point of interest is the development of relatively small filter units that can be located inside the containment. The concept of a new design for double containment having annular rooms between the steel containment and the concrete containment is discussed. Work related to the dismantling of decommissioned reactors and limited research for fuel reprocessing facilities are also noted

Non-destructive evaluation of water ingress in photovoltaic modules

Energy Technology Data Exchange (ETDEWEB)

Bora, Mihail; Kotovsky, Jack

2017-03-07

Systems and techniques for non-destructive evaluation of water ingress in photovoltaic modules include and/or are configured to illuminate a photovoltaic module comprising a photovoltaic cell and an encapsulant with at least one beam of light having a wavelength in a range from about 1400 nm to about 2700 nm; capture one or more images of the illuminated photovoltaic module, each image relating to a water content of the photovoltaic module; and determine a water content of the photovoltaic module based on the one or more images. Systems preferably include one or more of a light source, a moving mirror, a focusing lens, a beam splitter, a stationary mirror, an objective lens and an imaging module.

Some observations on the problem of jelly fish ingress in a power station cooling system at Kalpakkam, east coast of India

International Nuclear Information System (INIS)

Rajagopal, S.; Azariah, Jayapaul; Nair, K.V.K.

1989-01-01

The paper reports results of a study on the seasonal distribution and abundance of jelly fishes in the coastal waters of Kalpakkam in the context of their ingress into the cooling system of a power plant. Three species of jelly fishes Dactylometra quinquicirrha (L. agassiz), Crambionella stuhlmanni (Chun) and Chiropsalmus buitendijki (Horst) were found in such abundance as to cause blockage of the cooling water intake screens. The seasonal variation in the incidence of the jelly fishes clearly showed that the periods of maxima and minima were different for each species. During the period of study (February 1988 to April 1989) three maxima were noted - May, July and October. On any given single day, maximum quantity of jelly fishes collected from the travelling screens was 29 tonnes (21 July 1988). The data are discussed with respect of (i)qualitative and quantitative variations in the ingress of jelly fishes at Kalpakkam, (ii)operational problems associated with jelly fish ingress and (iii)possible approaches to combat the problem. (author). 1 tab., 4 figs., 9 ref s

Techniques for controlling air pollution from the operation of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1966-03-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

Structural dynamic and resistance to nuclear air blast

International Nuclear Information System (INIS)

Qureshi, S.M.

2003-01-01

A need exists to design protective shelters attached to specialized facilities against nuclear airbursts, explosive shocks and impacting projectiles. Designing such structures against nuclear and missile impact is a challenging task that needs to be looked into for design methodology formulation and practicability. Structures can be designed for overpressure pulsed generated by a nuclear explosion as well as the scabbing and perforation/punching of an impacting projectile. This paper discuses and formulates the methods of dynamic analysis and design required to undertake such a task. Structural resistance to peak overpressure pulse for a 20 KT weapons and smaller tactical nuclear weapons of 1 KT (16 psi, overpressure) size as a direct air blast overpressure has been considered in design of walls, beams and slabs of a special structure under review. The design of shear reinforcement as lacing is also carried out. Adopting the philosophy of strengthening and hardening can minimize the effect of air blast overpressure and projectile impact. The objective is to avoid a major structural failure. The structure then needs to be checked against ballistic penetration by a range of weapons or be required to resist explosive penetration from the charge detonated in contact with the structure. There is also a dire need to formulate protective guidelines for all existing and future critical facilities. (author)

Technical development of nuclear air cleaning in the People's Republic of China

International Nuclear Information System (INIS)

Li Xue Qun; Liu Hui; Wang Tie Shen; Xin Song Niam; Guo Liang Tian.

1985-01-01

In the past 20 years, with the utilization of nuclear technology in China, air cleaning techniques were developed to prevent the environment from pollution caused by radioactive materials and to ensure the safety of occupational personnel. The technical developments involve many fields including the manufacture of filter media and adsorbents; the application of filters and iodine adsorbers and the testing of them; the improvement of instruments and methods for aerosol concentration measurement; the retention of radioactive noble gases; and others. As nuclear power stations are to be built in China, nuclear air cleaning will be advancing more rapidly. Many programs have been scheduled, such as producing other types of adsorbers, moisture separators, nuclear grade HEPA filters that have excellent performance to resist adverse circumstances, and in-place testing for units of ventilation systems in nuclear facilities. These programs are discussed

Experience of air transport of nuclear fuel material in Japan

International Nuclear Information System (INIS)

Yamashita, T.; Toguri, D.; Kawasaki, M.

2004-01-01

Certified Reference Materials (hereafter called as to CRMs), which are indispensable for Quality Assurance and Material Accountability in nuclear fuel plants, are being provided by overseas suppliers to Japanese nuclear entities as Type A package (non-fissile) through air transport. However, after the criticality accident at JCO in Japan, special law defining nuclear disaster countermeasures (hereafter called as to the LAW) has been newly enforced in June 2000. Thereafter, nuclear fuel materials must meet not only to the existing transport regulations but also to the LAW for its transport

Proceedings of the 19th DOE/NRC nuclear air cleaning conference

International Nuclear Information System (INIS)

First, M.W.

1987-05-01

This document contains the papers and the associated discussions of the 19 DOE/NRC Nuclear Air Cleaning Conference. Sessions were devoted to (1) fire, explosion and accident analysis, (2) adsorption and iodine retention, (3) filters and filter testing, (4) standards and regulation, (5) treatment of radon, krypton, tritium and carbon-14, (6) ventilation and air cleaning in reactor operations, (7) dissolver off-gas cleaning, (8) adsorber fires, (9) nuclear grade carbon testing, (10) sampling and monitoring, and (11) field test experience. Individual papers were processed separately for the data base

Analysis on ingress of coolant event in vacuum vessel using modified TRAC-BF1 code

International Nuclear Information System (INIS)

Ajima, Toshio; Kurihara, Ryoichi; Seki, Yasushi

1999-08-01

The Transient Reactor Analysis Code (TRAC-BF1) was modified on the basis of ICE experimental results so as to analyze the Ingress of Coolant Event (ICE) in the vacuum vessel of a nuclear fusion reactor. In the previous report, the TRAC-BF1 code, which was originally developed for the safety analysis of a light water reactor, had been modified for the ICE of the fusion reactor. And the addition of the flat structural plate model to the VESSEL component and arbitrary appointment of the gravity direction had been added in the TRAC-BF1 code. This TRAC-BF1 code was further modified. The flat structural plate model of the VESSEL component was enabled to divide in multi layers having different materials, and a part of the multi layers could take a buried heater into consideration. Moreover, the TRAC-BF1 code was modified to analyze under the low-pressure condition close to vacuum within range of the steam table. This paper describes additional functions of the modified TRAC-BF1 code, analytical evaluation using ICE experimental data and the ITER model with final design report (FDR) data. (author)

Space Nuclear Thermal Propulsion (SNTP) Air Force facility

Science.gov (United States)

Beck, David F.

The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility.

Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

International Nuclear Information System (INIS)

Fish, J.F.

1979-01-01

Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

The actual practice of air cleaning in Belgian nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Goossens, W.R. [PEGO, Mol (Belgium)

1995-02-01

With 60% of its power generation from nuclear stations Belgium has 7 nuclear power stations in operation with a total capacity of 5.4 MWe. Enriched uranium is imported and converted to fuel assemblies. The actinides of reprocessed fuel are recycled as MOX fuel. A main waste conditioning operation has been performed in the PAMELA vitrifier. The actual practice of nuclear air cleaning in the Belgian PWR station DOEL-4 and in the PAMELA -vitrification plant for high level liquid waste is reviewed.

Twenty-second DOE/NRC nuclear air cleaning and treatment conference

International Nuclear Information System (INIS)

Bellamy, R.R.; Moeller, D.W.; First, M.W.

1992-01-01

The Twenty-Second Department of Energy/Nuclear Regulatory Commission Nuclear Air Cleaning and Treatment Conference was held Aug. 24-27, 1992, in Denver, Colo. A total of 224 air-cleaning specialists attended the conference. The United States and 12 foreign countries were represented, and the specialists were affiliated with government agencies, educational institutions, and all aspects of the nuclear industry, including utilities, architect engineers, equipment suppliers, and consultants. Several major topics were discussed, similar to areas covered at previous conferences: chemical processing off-gas cleaning; particulate filler developments, including filter testing, performance, and response to physical stress,adsorber testing and performance, including laboratory and in-place testing; waste management; system operation; codes and standards; and advanced nuclear power plants. The conference continued to provide an effective forum for direct interchange of information of both a practical and theoretical nature. International participation and interest continues, as evidenced by over 40% of the papers being sponsored by foreign interests and almost 20% of the attendees being from outside the United States. The potential for new, safer nuclear plants of an advanced design was an optimistic note during the conference. Regulatory authorities are playing a major role in providing guidance in the development of safety goals and other technical criteria for these new installations

Moisture ingress into electronics enclosures under isothermal conditions

International Nuclear Information System (INIS)

Staliulionis, Ž.; Jabbari, M.; Hattel, J. H.

2016-01-01

The number of electronics used in outdoor environment is constantly growing. The humidity causes about 19 % of all electronics failures and, especially, moisture increases these problems due to the ongoing process of miniaturization and lower power consumption of electronic components. Moisture loads are still not understood well by design engineers, therefore this field has become one of the bottlenecks in the electronics system design. The objective of this paper is to model moisture ingress into an electronics enclosure under isothermal conditions. The moisture diffusion model is based on a 1D quasi-steady state (QSS) approximation for Fick’s second law. This QSS approach is also described with an electrical analogy which gives a fast tool in modelling of the moisture response. The same QSS method is applied to ambient water vapour variations. The obtained results are compared to an analytical solution and very good agreement is found.

A study of air-operated valves in U.S. nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Rothberg, O. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Khericha, S. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Watkins, J. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Holbrook, M. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States)

2000-02-01

A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

A study of air-operated valves in U.S. nuclear power plants

International Nuclear Information System (INIS)

Rothberg, O.; Khericha, S.; Watkins, J.; Holbrook, M.

2000-01-01

A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

Effects of Oxidation on Oxidation-Resistant Graphite

Energy Technology Data Exchange (ETDEWEB)

Windes, William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Rebecca [Idaho National Lab. (INL), Idaho Falls, ID (United States); Carroll, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-05-01

The Advanced Reactor Technology (ART) Graphite Research and Development Program is investigating doped nuclear graphite grades that exhibit oxidation resistance through the formation of protective oxides on the surface of the graphite material. In the unlikely event of an oxygen ingress accident, graphite components within the VHTR core region are anticipated to oxidize so long as the oxygen continues to enter the hot core region and the core temperatures remain above 400°C. For the most serious air-ingress accident which persists over several hours or days the continued oxidation can result in significant structural damage to the core. Reducing the oxidation rate of the graphite core material during any air-ingress accident would mitigate the structural effects and keep the core intact. Previous air oxidation testing of nuclear-grade graphite doped with varying levels of boron-carbide (B4C) at a nominal 739°C was conducted for a limited number of doped specimens demonstrating a dramatic reduction in oxidation rate for the boronated graphite grade. This report summarizes the conclusions from this small scoping study by determining the effects of oxidation on the mechanical strength resulting from oxidation of boronated and unboronated graphite to a 10% mass loss level. While the B4C additive did reduce mechanical strength loss during oxidation, adding B4C dopants to a level of 3.5% or more reduced the as-fabricated compressive strength nearly 50%. This effectively minimized any benefits realized from the protective film formed on the boronated grades. Future work to infuse different graphite grades with silicon- and boron-doped material as a post-machining conditioning step for nuclear components is discussed as a potential solution for these challenges in this report.

Research on water chemistry in a nuclear power plant

International Nuclear Information System (INIS)

Chae, Sung Ki; Yang, Kyung Rin; Kang, Hi Dong; Koo, Je Hyoo; Hwang, Churl Kew; Lee, Eun Hee; Han, Jung Ho; Kim, Uh Chul; Kim, Joung Soo; Song, Myung Ho; Lee, Deok Hyun; Jeong, Jong Hwan

1986-12-01

To prevent the corrosion problems on important components of nuclear power plants, the computerization methods of water chemistry and the analyses of corrosion failures were studied. A preliminary study on the computerization of water chemistry log-sheet data was performed using a personal computer with dBASE-III and LOTUS packages. Recent technical informations on a computerized online chemistry data management system which provides an efficient and thorough method of system-wide monitoring of utility's secondary side chemistry were evaluated for the application to KEPCO's nuclear power plants. According to the evaluation of water chemistry data and eddy current test results, it was likely that S/G tube defect type was pitting. Pitting is believed to result from excess oxygen in make-up and air ingress, sea-water ingress bycondenser leak, and copper in sludge. A design of a corrosion tests apparatus for the tests under simulated operational conditions, such as water chemistry, water flow, high temperature and pressure, etc., of the plant has been completed. The completion of these apparatus will make it possible to do corrosion tests under the conditions mentioned above to find out the cause of corrosion failures, and to device a counter measure to these. The result of corrosion tests with alloy-600 showed that the initiation of pits occurred most severely around 175 deg C which is lower than plant-operation temperature(300 deg C) while their propagation rate had trend to be maximum around 90 deg C. It was conformed that the use of Cu-base alloys in a secondary cooling system accelerates the formation of pits by the leaking of sea-water and expected that the replacement of them can reduce the failures of S/G tubes by pitting. Preliminary works on the examination of pit-formed specimens with bare eyes, a metallurgical microscope and a SEM including EDAX analysis were done for the future use of these techniques to investigate S/G tubes. Most of corrosion products

Development of Air Dispersion Modeling for Future Nuclear Plant in Malaysia

International Nuclear Information System (INIS)

Mohd Nahar Othman

2011-01-01

The impact development of Nuclear power plant in Malaysia, can be very negative to the nearby population, causing public restlessness and consequently affecting the image of the authorities in the countries. The precise source of the pollution from the nuclear power plant must be determined, pollution emission level and the meteorological conditions are needed to predict and established the ambient air to the save level at the perimeter fence of the plant and address it with respect to the radiological ambient standards. Upon modeling using an established package as well as site measurements, the radiological level at the perimeter fence of the plant must deduced and lower than the normal ambient level. Based on this issue, a modeling study was made in vicinity of Malaysian Nuclear Agency TRIGA reactor in the area of Bangi, Selangor to evaluate the possibility of movement of air around the area and their impact. This paper will address and discuss the modeling base on the data getting from Meteorological Department such as measurement of wind speed, temperature, humidity, ambient air radiological concentration and ect. The purpose of Air Dispersion Modeling is to establish the critical ambient emission level, as well as radiological modeling. The focus will be made on exploring the use of Ausplume modeling to develop correlations between the radiological concentrations, chemical compositions and ambient model for emission controls. (author)

Safety assessment for electricity generation failure accident of gas cooled nuclear power plant using system dynamics (SD) method

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho [Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering

2013-04-15

The power production failure happens in the loss of coolant of the nuclear power plants (NPPs). The air ingress is a serious accident in gas cooled NPPs. The quantification of the study performed by the system dynamics (SD) method which is processed by the feedback algorithms. The Vensim software package is used for the simulation, which is performed by the Monte-Carlo method. Two kinds of considerations as the economic and safety properties are important in NPPs. The result shows the stability of the operation when the power can be decided. The maximum value of risk is the 11.77 in 43rd and the minimum value is 0.0 in several years. So, the success of the circulation of coolant is simulated by the dynamical values. (orig.)

Air box shock absorber for a nuclear reactor

International Nuclear Information System (INIS)

Pradhan, A.V.; George, J.A.

1977-01-01

Disclosed is an air box type shock absorber primarily for use in an ice condenser compartment of a nuclear reactor. The shock absorber includes a back plate member and sheet metal top, bottom, and front members. The front member is prefolded, and controlled clearances are provided among the members for predetermined escape of air under impact and compression. Prefolded internal sheet metal stiffeners also absorb a portion of the kinetic energy imparted to the shock absorber, and limit rebound. An external restraining rod guided by restraining straps insures that the sheet metal front member compresses inward upon impact. 6 claims, 11 figures

Nuclear air cleaning: the need for a change in emphasis

International Nuclear Information System (INIS)

Carbaugh, E.H.

1982-11-01

The nuclear industry now has over 35 years of experience in nuclear air cleaning. This experience covers technology development, system design, operations, and maintenance. Much of the past experience has been directed towards technology development with particular emphasis on high efficiency particulate air (HEPA) filters. Implementation of this technology has lagged its development by a number of years. A recent study examines the cause and frequencies of HEPA filter changeouts and failures. These data lead to a conclusion that a shift in emphasis from technology development to the training of personnel and the designing and maintaining of such systems is needed. Some highlights of the data and a discussion of topics which should be addressed in training will be presented

Nuclear air cleaning: the need for a change in emphasis

International Nuclear Information System (INIS)

Carbaugh, E.H.

1983-01-01

The nuclear industry now has over 35 years of experience in nuclear air cleaning. This experience covers technology development, system design, operations, and maintenance. Much of the past experience has been directed towards technology development with particular emphasis on high efficiency particulate air (HEPA) filters. Implementation of this technology has lagged its development by a number of years. A recent study examines the causes and frequencies of HEPA filter changeouts and failures. These data lead to a conclusion that a shift in emphasis from technology development to the training of personnel and the designing and maintaining of such systems is needed. Some highlights of the data and a discussion of topics which should be addressed in training will be presented. 7 references, 5 tables

The transgressive-regressive cycle of the Romualdo Formation (Araripe Basin): Sedimentary archive of the Early Cretaceous marine ingression in the interior of Northeast Brazil

Science.gov (United States)

Custódio, Michele Andriolli; Quaglio, Fernanda; Warren, Lucas Veríssimo; Simões, Marcello Guimarães; Fürsich, Franz Theodor; Perinotto, José Alexandre J.; Assine, Mario Luis

2017-08-01

Geologic events related to the opening of the South Atlantic Ocean deeply influenced the sedimentary record of the Araripe Basin. As consequence, upper stratigraphic units of the basin record a marine ingression in northeastern Brazil during the late Aptian. The timing and stratigraphic architecture of these units are crucial to understand the paleogeography of Gondwana and how the proto-Atlantic Ocean reached interior NE Brazil during the early Cretaceous. This marine ingression is recorded in the Araripe Basin as the Romualdo Formation, characterized by a transgressive-regressive cycle bounded by two regional unconformities. In the eastern part of the basin, the Romualdo depositional sequence comprises coastal alluvial and tide-dominated deposits followed by marine transgressive facies characterized by two fossil-rich intervals: a lower interval of black shales with fossil-rich carbonate concretions (Konservat-Lagerstätten) and an upper level with mollusk-dominated shell beds and shelly limestones. Following the marine ingression, an incomplete regressive succession of marginal-marine facies records the return of continental environments to the basin. The stratigraphic framework based on the correlation of several sections defines a transgressive-regressive cycle with depositional dip towards southeast, decreasing in thickness towards northwest, and with source areas located at the northern side of the basin. The facies-cycle wedge-geometry, together with paleocurrent data, indicates a coastal onlap towards NNW. Therefore, contrary to several paleogeographic scenarios previously proposed, the marine ingression would have reached the western parts of the Araripe Basin from the SSE.

AEC Regulatory view of the reliability of air cleaning systems in nuclear facilities

International Nuclear Information System (INIS)

Bellamy, R.R.; Zavadoski, R.W.

1975-01-01

Air cleaning systems in nuclear facilities can be divided into three categories: ventilation exhaust systems, containment atmosphere cleanup systems, and process offgas systems. These systems have been the subject of numerous reports, regulatory guides, discussions, and meetings. Some of the analyses have been critical of the operation and design of these air cleaning systems--in particular, the engineered safety features containment atmosphere cleanup systems. Although for the most part the criticism is applicable, and recognizing that there are a number of unresolved issues pertaining to gaseous waste management systems, there are data to show that air cleaning systems in use in nuclear facilities are performing their intended function. (U.S.)

Air pollution and international law: a subject important to nuclear power

International Nuclear Information System (INIS)

Rose, D.J.

1985-01-01

An increasingly important advantage of nuclear power is its minimal air pollution, in particular the absence of combustion products such as acid rain and carbon dioxide. Developing a consensus about acceptable limits of such pollutants is a slow process that culminates in domestic an international agreements. Therefore, the pace of adoption of new technologies, nuclear power included, is often controlled by the level and intensity of debate, rather than by the technology alone. The state of understanding and consensus about local and long-range transboundary air pollution is therefore germane to the nuclear sector. Progress over the past several decades, mainly between the United States and Canada and within Europe, in developing a more comprehensive and effective international consensus, both informal and formal, is reviewed. There appears to be a trend toward more effective international participation in seeking a less-polluting world, albeit it is punctuated at times by unconcern

Compressed-air and backup nitrogen systems in nuclear power plants

International Nuclear Information System (INIS)

Hagen, E.W.

1982-07-01

This report reviews and evaluates the performance of the compressed-air and pressurized-nitrogen gas systems in commercial nuclear power units. The information was collected from readily available operating experiences, licensee event reports, system designs in safety analysis reports, and regulatory documents. The results are collated and analyzed for significance and impact on power plant safety performance. Under certain circumstances, the fail-safe philosophy for a piece of equipment or subsystem of the compressed-air systems initiated a series of actions culminating in reactor transient or unit scram. However, based on this study of prevailing operating experiences, reclassifying the compressed-gas systems to a higher safety level will neither prevent (nor mitigate) the reoccurrences of such happenings nor alleviate nuclear power plant problems caused by inadequate maintenance, operating procedures, and/or practices. Conversely, because most of the problems were derived from the sources listed previously, upgrading of both maintenance and operating procedures will not only result in substantial improvement in the performance and availability of the compressed-air (and backup nitrogen) systems but in improved overall plant performance

Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

Energy Technology Data Exchange (ETDEWEB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1991-02-01

The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

Tritium concentration in ambient air around Kaiga Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Srinivas S Kamath

2018-01-01

Full Text Available Tritium (3H is one of the important long-lived radioisotopes in the gaseous effluent from nuclear power plants. In this article, we present the results of 3H monitoring in ambient air samples around the Kaiga Nuclear Power Plant, on the West Coast of India. Air samples were collected by moisture condensation method and the 3H concentration was determined by liquid scintillation spectrometry. The 3H concentration in the 2.3–15 km zone of the power plant varied in the range of <0.04–6.64 Bq m−3 with a median of 0.67 Bq m−3. The samples collected from the 2.3–5 km zone of the power plant exhibit marginally higher concentration when compared to the 5–10 km and 10–15 km zones, which is as expected. The values observed in the present study for Kaiga region are similar to those reported from other nuclear power plants, both within India and other parts of the world.

Air quality assessment in the vicinity of nuclear and thermal power stations

International Nuclear Information System (INIS)

Sivaramasundaram, K.; Vijay Bhaskar, B.; Muthusubramanian, P.; Rajan, M.P.; Hegde, A.G.

2007-01-01

The status and ranking of any country, in the context of globalisation, is decided by its economic progress, which is directly linked into power generation. The power is generated by many routes and the nuclear and thermal routes are noteworthy among them. As the power production and its associated activities may cause qualitative deterioration, it is essential to study the impact of power production on atmospheric environment. In this connection, a comparative study has been carried out to assess the air quality with special reference to criteria pollutants in the vicinity of nuclear and thermal power stations. In the present investigation, the air samples are collected on weekly basis and the pollutants such as sulphur dioxide (SO 2 ), nitrogen oxides (NOx), carbon monoxide (CO), suspended particulate matter (SPM) and respirable particulate matter (RPM) are estimated by adopting standard procedures set by United States-Environmental Protection Agency (US-EPA) and Central Pollution Control Board (CPCB). As the micro meteorological parameters influence on the status of air quality, simultaneous measurements of these parameters are also carried, out during sampling. It is studied that estimated concentrations of all criteria pollutants in the vicinity of these power stations are within the permissible limits set by CPCB. On the basis of the generated database pertaining to the concentrations of criteria air pollutants in the vicinity of nuclear and thermal power stations, it is concluded that nuclear power production may be considered as a viable option in terms of environmental protection in our country. (author)

Chloride Ingress in Concrete with Different Age at Time of First Chloride Exposure

DEFF Research Database (Denmark)

Hansen, Esben Østergaard; Iskau, Martin Riis; Hasholt, Marianne Tange

2016-01-01

Concrete structures cast in spring have longer time to hydrate and are therefore denser and more resistant to chloride ingress when first subjected to deicing salts in winter than structures cast in autumn. Consequently, it is expected that a spring casting will have a longer service life....... This hypothesis is investigated in the present study by testing drilled cores from concrete cast in 2012 and 2013 on the Svendborgsund Bridge. The cores are subject to petrographic examination and mapping of chloride profiles. Moreover, chloride migration coefficients have been measured. The study shows...

A simple method to determine Tr concentrations in the moisture of the exhaust air of nuclear facilities and in the ambient air

International Nuclear Information System (INIS)

Weber, H.W.; Schuettelkopf, H.

1983-04-01

In the course of nuclear power plant operation radioactive tritium is generated which is released to the environment as HTO via the exhaust air and the liquid effluents. Measurement and balancing of the tritium emissions are required in order to be able to evaluate the resulting radiation exposure of the population. For determination of the HTO emission the humidity of the measured air is absorbed at a rod shaped molecular sieve of 1/16'' mesh size. The desiccant is contacted with T-free water and the T activity concentration of the water is determined after 3 H/ 1 H isotope exchange. The rod shaped molecular sieves are suited for use under this method on account of their drying capacity largely independent of temperature and air humidity and the good handling capability. The detection limit is at 19 Bq HTO/m 3 air. The exhaust air from several 3 H-emitters of the Karlsruhe Nuclear Research Center was monitored by this method for its HTO content and the results were compared with the values measured at existing points of measurement. The good results have been the reason for the application of such collectors in the routine T-measurement performed within the framework of exhaust air monitoring on the site of the Karlsruhe Nuclear Research Center. (orig./HP) [de

Determination of the radioiodine species in the exhaust air of nuclear facilities

International Nuclear Information System (INIS)

Deuber, H.

1977-01-01

Using the selective I 2 sorption materials DSM 10 and DSM 11 measurements were performed with radioiodine species samplers in the exhaust air of a research reactor and of several nuclear power stations (BWR, PWR). The radioiodine species samplers were used upstream and downstream of iodine filters (containment exhaust air stand-by filter, shutoff room exhaust air filter) as well as in the exhaust air of the stack. The results obtained by use of DSM 10 and DSM 11 generally agreed. The percentage of aerosol iodine was low in all cases ( [de

Sizing of air cleaning systems for access to nuclear plant spaces

International Nuclear Information System (INIS)

Estreich, P.J.

A mathematical basis is developed to provide the practicing engineer with a method for sizing air-cleaning systems for nuclear facilities. In particular, general formulas are provided to relate cleaning and contamination dynamics of an enclosure such that safe conditions are obtained when working crews enter. Included in these considerations is the sizing of an air-cleaning system to provide rapid decontamination of airborne radioactivity. Multiple-nuclide contamination sources, leak rate, direct radiation, contaminant mixing efficiency, filter efficiencies, air-cleaning-system operational modes, and criteria for maximum permissible concentrations are integrated into the procedure. (author)

Biophysical processes leading to the ingress of temperate fish larvae into estuarine nursery areas: A review

Science.gov (United States)

Teodósio, Maria Alexandra; Paris, Claire B.; Wolanski, Eric; Morais, Pedro

2016-12-01

A series of complementary hypotheses have been proposed to explain the recruitment of marine and temperate pelagic fish larvae originated from pelagic eggs in coastal environments. In this review, we propose a new and complementary hypothesis describing the biophysical processes intervening in the recruitment of temperate fish larvae into estuaries. This new hypothesis, the Sense Acuity And Behavioral (SAAB) hypothesis, recognizes that recruitment is unlikely if the larvae drift passively with the water currents, and that successful recruitment requires the sense acuity of temperate fish larvae and their behavioral response to the estuarine cues present in coastal areas. We propose that temperate fish larvae use a hierarchy of sensory cues (odor, sound, visual and geomagnetic cues) to detect estuarine nursery areas and to aid during navigation towards these areas. The sensorial acuity increases along ontogeny, which coincides with increased swimming capabilities. The swimming strategies of post-flexion larvae differ from offshore areas to the tidal zone. In offshore areas, innate behavior might lead larvae towards the coast guided by a sun compass or by the earth's geomagnetic field. In areas under limited influence of estuarine plumes (either in energetic nearshore areas or offshore), post-flexion larvae display a searching swimming behavior for estuarine disconnected patches (infotaxis strategy). After finding an estuarine plume, larvae may swim along the increasing cue concentration to ingress into the estuary. Here, larvae exhibit a rheotaxis behavior and avoid displacement by longshore currents by keeping bearing during navigation. When larvae reach the vicinity of an estuary, merging diel rhythms with feeding and predator avoidance strategies with tidally induced movements is essential to increase their chances of estuarine ingress. A fish larva recruitment model developed for the Ria Formosa lagoon supports the general framework of the SAAB hypothesis. In

36 CFR 14.5 - Nature of interest granted; settlement on right-of-way; rights of ingress and egress.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Nature of interest granted; settlement on right-of-way; rights of ingress and egress. 14.5 Section 14.5 Parks, Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR RIGHTS-OF-WAY Nature of Interest § 14.5 Nature...

The investigation on compressed air quality analysis results of nuclear power plants

International Nuclear Information System (INIS)

Sung, K. B.; Kim, H. K.; Kim, W. S.

2000-01-01

The compressed air system of nuclear power plants provides pneumatic power for both operation and control of various plant equipment, tools, and instrumentation. Included in the air supply systems are the compressors, coolers, moisture separators, dryers, filters and air receiver tanks that make up the major items of equipment. The service air system provides oil-free compressed air for general plant and maintenance use and the instrument air system provides dry, oil-free, compressed air for both nonessential and essential components and instruments. NRC recommended the periodic checks on GL88-14 'Instrument air supply system problems affecting safety-related equipment'. To ensure that the quality of the instrument air is equivalent to or exceeds the requirement s of ISA-S7.3(1975), air samples are taken at every refueling outage and analyzed for moisture, oil and particulate content. The over all results are satisfied the requirements of ISA-S7.3

Review of failures in nuclear air cleaning systems (1975--1978)

International Nuclear Information System (INIS)

Moeller, D.W.

1979-01-01

During the period from January 1, 1975 through June 30, 1978, over 9,000 Licensee Event Reports (LERs) pertaining to the operation of commercial light water nuclear power plants in the US were reported to the Nuclear Regulatory Commission. Of these reports, over 1,200 (approximately 13%) pertained to failures in air monitoring, ventilating and cleaning systems. For BWR installations, over half of the reported events related to failures in equipment for monitoring the performance of air cleaning systems as contrasted to failures in the systems themselves. In PWR installations, failures in monitoring equipment amounted to about 32% of the total. Reported problem areas in BWR installations included the primary containment and standby gas treatment and off-gas systems, as well as the High Pressure Coolant Injection and Reactor Core Isolation Systems. For PWR installations, reported problem areas included primary containment and associated spray systems and waste processing equipment. Although data on reported failures in power reactor installations can be interpreted in a variety of ways, one message is clear. There is a need for research on the development of more reliable equipment for sampling and monitoring air systems. Equipment that provides inaccurate data on the performance of such systems can lead to as many problems as inadequacies in the systems themselves

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

International Nuclear Information System (INIS)

1995-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

International Nuclear Information System (INIS)

1966-01-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

High efficiency steel filters for nuclear air cleaning

International Nuclear Information System (INIS)

Bergman, W.; Conner, J.; Larsen, G.; Lopez, R.; Turner, C.; Vahla, G.; Violet, C.; Williams, K.

1991-01-01

The authors have, in cooperation with industry, developed high-efficiency filters made from sintered stainless-steel fibers for use in several air-cleaning applications in the nuclear industry. These filters were developed to overcome the failure modes in present high-efficiently particulate air (HEPA) filters. HEPA filters are made from glass paper and glue, and they may fail when they get hot or wet and when they are overpressured. In developing steel filters, they first evaluated the commercially available stainless-steel filter media made from sintered powder and sintered fiber. The sintered-fiber media performed much better than sintered-powder media, and the best media had the smallest fiber diameter. Using the best media, prototype filters were then built for venting compressed gases and evaluated in their automated filter tester

Air Force Nuclear Enterprise Organization: A Case Study

Science.gov (United States)

2016-09-15

changes. To address the objectives of this study, five investigative questions ( IQ ) are posed: IQ1. What constitutes the Air Force Nuclear Enterprise...are an effective tool being used to raise the level of training. But it is not only necessary to move away from training that merely checks a box...down to an authoritative brain trust of just a few pertinent players (e.g. AFGSC/CC, HAF/A10 Director, AFNWC/CC, etc). As this study has portrayed

Supply air filters after the nuclear reactor accident at Chernobyl

International Nuclear Information System (INIS)

Bonka, H.

1989-01-01

In the case of increased activity concentration in the air supply air filters are the facility compounds where enhanced activity is collected. Therefore, it was understandable that the people put questions about the doses caused by supply air filters after the nuclear reactor accident at Chernobyl. When comparing the local dose rate at a distance of 1 m in front of filters with the outdoor local dose rate due to dry deposited radionuclides, nearly the same local dose rate results assuming an air flow rate of approx. 60 m 3 /h. Supposing a 10 hours stay at a distance of 1 m in front of filters and an air flow rate of approx. 5000 m 3 /h the same dose is obtained after a 10 days delay as the dose due to outdoor inhalation. At Aachen, the local dose rate near to filters increased up to approx. 10 μSv/h. After a suitable time delay of one month filters could be rejected like normal waste. A review is given on individual measured values

Air contamination measurements for the evaluation of internal dose to workers in nuclear medicine departments

Science.gov (United States)

De Massimi, B.; Bianchini, D.; Sarnelli, A.; D'Errico, V.; Marcocci, F.; Mezzenga, E.; Mostacci, D.

2017-11-01

Radionuclides handled in nuclear medicine departments are often characterized by high volatility and short half-life. It is generally difficult to monitor directly the intake of these short-lived radionuclides in hospital staff: this makes measuring air contamination of utmost interest. The aim of the present work is to provide a method for the evaluation of internal doses to workers in nuclear medicine, by means of an air activity sampling detector, to ensure that the limits prescribed by the relevant legislation are respected. A continuous air sampling system measures isotope concentration with a Nal(TI) detector. Energy efficiency of the system was assessed with GEANT4 and with known activities of 18F. Air is sampled in a number of areas of the nuclear medicine department of the IRST-IRCCS hospital (Meldola- Italy). To evaluate committed doses to hospital staff involved (doctors, technicians, nurses) different exposure situations (rooms, times, radionuclides etc) were considered. After estimating the intake, the committed effective dose has been evaluated, for the different radionuclides, using the dose coefficients mandated by the Italian legislation. Error propagation for the estimated intake and personal dose has been evaluated, starting from measurement statistics.

Dissolved air flotation for treating wastewater of the nuclear industry. Preliminary results

International Nuclear Information System (INIS)

Ortiz-Oliveros, H.B.; Jimenez-Moleon, M.C.; Cruz-Gonzalez, D.

2012-01-01

Preliminary testing of dissolved air flotation (DAF) for wastewater treatment is presented. A combined coagulation-flocculation/DAF column system is used to remove oil and 60 Co from nuclear industry wastewater. In this work, operational conditions and coagulant/flocculant concentrations are optimized by varying pH. Determinations of air-solids ratio (G/S), retention time (θ), pressure (P), volume of depressurized air-water mixture (V), turbidity and 60 Co concentrations are reported. The effect of the treatment on the efficiency of separation of oily residues is also discussed. The results establish that the coagulant/flocculant system, formed by a modified polyamine (25 mgL -1 ) and a slightly cationic polyacrylamide (1.5 mgL -1 ), under specific operational conditions (pH = 7, mixing intensity Im 1 = 300 s -1 and Im 2 = 30 s -1 ), allowed the destabilization of colloidal matter, resulting in resistant flocs. It was concluded that by using G/S = 0.3, θ = 15 min, P = 620 kPa and V = 0.0012 m 3 , the greatest percentage removals of oil, turbidity, total cobalt and 60 Co were obtained. These preliminary results then show that dissolved air flotation represents a good alternative for treatment of nuclear industry wastewater contaminated with radionuclides. (author)

Numerical analysis on ingress-of-coolant events in fusion reactors with TRAC-PF1 code

International Nuclear Information System (INIS)

Ose, Yasuo; Takase, Kazuyuki; Akimoto, Hajime

2000-01-01

As for accident events related with thermal-hydraulics, in a fusion experimental reactor an ingress-of-coolant event (ICE) and a loss-of-vacuum-accident event (LOVA) should be considered. An integrated ICE/LOVA test apparatus is under planning in order to estimate quantitatively heat transfer and fluid flow characteristics under ICE and LOVA events. This study was carried out to predict numerically the thermal-hydraulic characteristics in fusion reactors at the ICE events before construction of the integrated ICE/LOVA test apparatus. The TRAC-PF1 code, which was originally developed for the thermal-hydraulic safety analysis in light water reactors, was used. The numerical analyses were performed for two kinds of system configuration with/without a pressure-suppression tank:the former for is investigation of the pressure rise characteristics and two-phase flow behavior; the latter for estimation of an effect of the pressure reduction due to the pressure-suppression tank. From the present analytical results, effects of the ingress water flow rate and vessel temperatures on the pressure rise ware clarified quantitatively. Furthermore, the pressure-rise suppression effect due to the vapor condensation in the pressure-suppression tank was predicted numerically. In addition, the useful information regarding to the design of the integrated ICE/LOVA test apparatus and the knowledge with respect to the effective usage of the TRAC-PF1 code were obtained through the present numerical study. (author)

Long-term performance of structures comprising nuclear power plants PART 1: Deterioration assessment of nuclear power station buildings PART 2: Long-term stability and the leak-tightness of reactor containments

International Nuclear Information System (INIS)

Pocock, D.C.; Worthington, J.C.; Oberpichler, R.; Van Exel, H.; Beukelmann, D.; Huth, R.; Rose, B.

1990-01-01

The objective of this research was to study the long-term performance of structures comprising nuclear power plants. The time period of interest for this study is 140 years (this figure is based on maximum periods of 40 years for operation and 100 years of storage). It was divided in two parts: - the first based on four UK nuclear power plants examine the principle deterioration mechanism of reinforced structure which is chloride ingress and carbonation penetration - the second based on 2 German nuclear power plants examine the long term behaviour of reinforced and prestressed concrete and also the corrosion of steel containments with particular reference on plastic seals and potential risk areas

Use of a multi-species reactive transport model to simulate chloride ingress in mortar exposed to NaCl solution or sea-water

DEFF Research Database (Denmark)

Jensen, Mads Mønster; De Weerdt, K.; Johannesson, Björn

2015-01-01

Simulations of ion ingress in Portland cement mortar using a multi-species reactive mass transport model are compared with experimental test results. The model is an extended version of the Poisson–Nernst–Planck equations, accounting for chemical equilibrium. Saturated mortar samples were exposed...

Without the nuclear, would air be more breathable?

International Nuclear Information System (INIS)

Le Ngoc, Boris

2015-01-01

As pollution peaks are noticed in all big cities with dramatic consequences on health and on the economy, this article first outline these consequences of the use of fossil energies: 480.000 premature deaths in OECD countries due to the consequences of atmospheric pollution which results in heart and respiratory diseases, coronary diseases, cerebrovascular accidents or lung cancers, and nearly 120.000 deaths in dwellings, mainly in developing countries, due to the use of solid fuels for cooking and heating. Figures of the assessment of the economic cost and health impact of air pollution in 53 European countries are given. The author then outlines that the use of nuclear energy does not generate these pollutions: according to a study, nuclear energy avoided 1.8 million deaths between 1971 and 2009, and its replacement by coal would result in 4 to 7 million additional deaths

The high efficiency steel filters for nuclear air cleaning

International Nuclear Information System (INIS)

Bergman, W.; Larsen, G.; Lopez, R.; Williams, K.; Violet, C.

1990-08-01

We have, in cooperation with industry, developed high-efficiency filters made from sintered stainless-steel fibers for use in several air-cleaning applications in the nuclear industry. These filters were developed to overcome the failure modes in present high-efficiency particulate air (HEPA) filters. HEPA filters are made from glass paper and glue, and they may fail when they get hot or wet and when they are overpressured. In developing our steel filters, we first evaluated the commercially available stainless-steel filter media made from sintered powder and sintered fiber. The sintered-fiber media performed much better than sintered-powder media, and the best media had the smallest fiber diameter. Using the best media, we then built prototype filters for venting compressed gases and evaluated them in our automated filter tester. 12 refs., 20 figs

The Transit Ingress and the Tilted Orbit of the Extraordinarily Eccentric Exoplanet HD 80606b

Science.gov (United States)

Winn, Joshua N.; Howard, Andrew W.; Johnson, John A.; Marcy, Geoffrey W.; Gazak, J. Zachary; Starkey, Donn; Ford, Eric B.; Colon, Knicole D.; Reyes, Francisco; Nortmann, Lisa;

Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements during Fire Conditions in Nuclear Applications

International Nuclear Information System (INIS)

Rashad, S.; El-Fawal, M.; Kandil, M.

2013-01-01

The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the fire protection for the ventilation system to achieve safety and adequate protection in nuclear applications facilities during fire and accidental criticality conditions.The main purpose of this research is to assist ventilation engineers and experts in nuclear installations for safe operation and maintaining ventilation and air cleaning system during fire accident in nuclear facilities. The research focuses on fire prevention and protection of the ventilation systems in nuclear facilities. High-Efficiency particulate air (HEPA) filters are extremely susceptible to damage when exposed to the effects of fire, smoke, and water; it is the intent of this research to provide the designer with the experience gained over the years from hard lessons learned in protecting HEPA filters from fire. It describes briefly and evaluates the design safety features, constituents and working conditions of ventilation and air cleaning system in nuclear and radioactive industry.This paper provides and

Phenomenology of deflagration and detonation of hydrogen-air mixtures in water cooled nuclear power plants

International Nuclear Information System (INIS)

Lombardi, G.

1984-01-01

This paper summarizes fundamentals of the flammability of the hydrogen-air mixtures and hydrogen-air containing added steam or other inerting agent. The flammability behaviour of such gaseous mixtures is described with reference to physical and chemical conditions close enough to those expected in the containment of a nuclear reactor during a LOCA

Licensing Air and Transboundary Shipments of Spent Nuclear Fuel

International Nuclear Information System (INIS)

Komarov, S.V.; Budu, M.E.; Derganov, D.V.; Savina, O.A.; Bolshinsky, I.M.; Moses, S.D.; Biro, L.

2016-01-01

Since 1996 the IAEA TS-R-1 regulation included new requirements applicable to transport of fissile materials by air. The later 2005 and 2009 editions confirmed the validity of those provisions. Despite the fact that the IAEA TS-R-1 allows for air shipments of SNF in Type B and Type C packages, the examples of such shipments are not abundant. Nuclear regulatory bodies and transport safety experts are cautious about air shipments of SNF. Why so? What are the risks? What are the alternatives? In this new regulatory framework, in 2009, two air shipments in Type B packages of Research Reactor (RR) Spent Nuclear Fuel (SNF) from Romania and Libya were performed under the U.S. DOE/NNSA RRRFR Program. The first licensing process of such shipment brought up many questions about package and shipment safety from the licensing experts' side and so the scope of analyses exceeded the requirements of IAEA. Under the thorough supervision of Rosatom and witnessed by DOE and CNCAN, all questions were answered by various strength analyses and risk evaluations. But the progress achieved didn't stop here. In 2010-2011, an energy absorption container (EAC) with titanium spheres as absorbers based on the SKODA VPVR/M cask was designed as the first Type C package in the world destined for RR SNF, currently under approval process. At the same time, intense preparations for the safe removal of the Russian-origin damaged RR SNF from Serbia, Vinca were in progress. The big amount of SNF and its rapidly worsening condition imposed as requirements to organize only one shipment as fast as possible, i.e. using at the maximum extent the entire experience available from other SNF shipments. The long route, several transit countries and means of transport, two different casks, new European regulations and many other issues resulted for the Serbian shipment in one of the most complex SNF shipments’ licensing exercise. This paper shows how the international regulatory framework ensures the

Determination of air pollutants by nuclear chemical analysis

International Nuclear Information System (INIS)

Lesny, J.; Toelgyessy, J.

1975-01-01

Nuclear analytical methods are discussed with a view to their applicability in the determination of air pollutants. It is shown that some methods (use of radioactive kryptonates in automatic analyzers, application of activation analysis, X-ray fluorescence methods) are developed in theory and proven in practice in such an extent to be widely used in the near future in the control of the environment. Many other methods are becoming increasingly important for the solution of specific problems of environmental protection (such as the control of sudden environmental contamination in the proximity of chemical plants and industrial centers). (author)

ASME N511-19XX, Standard for periodic in-service testing of nuclear air treatment, heating, ventilating and air conditioning systems

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-01

A draft version of the Standard is presented in this document. The Standard covers the requirements for periodic in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities. The Standard provides a basis for the development of test programs and does not include acceptance criteria, except in cases where the results of one test influence the performance of other tests. The Standard covers general inspection and test requirements, reference values, inspection and test requirements, generic tests, acceptance criteria, in-service test requirements, testing following an abnormal incident, corrective action requirements, and quality assurance. Mandatory appendices provide a visual inspection checklist and four test procedures. Non-mandatory appendices provide additional information and guidance on mounting frame pressure leak test procedure, corrective action, challenge gas substitute selection criteria, and test program development. 8 refs., 10 tabs.

ASME N511-19XX, Standard for periodic in-service testing of nuclear air treatment, heating, ventilating and air conditioning systems

International Nuclear Information System (INIS)

1997-01-01

A draft version of the Standard is presented in this document. The Standard covers the requirements for periodic in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities. The Standard provides a basis for the development of test programs and does not include acceptance criteria, except in cases where the results of one test influence the performance of other tests. The Standard covers general inspection and test requirements, reference values, inspection and test requirements, generic tests, acceptance criteria, in-service test requirements, testing following an abnormal incident, corrective action requirements, and quality assurance. Mandatory appendices provide a visual inspection checklist and four test procedures. Non-mandatory appendices provide additional information and guidance on mounting frame pressure leak test procedure, corrective action, challenge gas substitute selection criteria, and test program development. 8 refs., 10 tabs

Use of nuclear and nuclear-related analytical techniques in studies of trace and minor elements in air pollution

International Nuclear Information System (INIS)

Smodis, Borut; Stropnik, Boris

1994-01-01

Among nuclear and nuclear-related analytical techniques, neutron activation and X-ray fluorescence analysis are particularly useful for environmental studies owing to their non-destructive character and multi-element capability. In this work, procedures for k o -standardized instrumental neutron activation analysis (INAA) and energy-dispersive X-ray fluorescence (EDXRF) spectrometry for trace and minor elements in air pollution studies were investigated. The methods applied were validated by the analysis of suitable reference materials. Using INAA, 20 experimentally obtained elemental values out of 21 certified and all 29 experimentally obtained values compared with 'consensus' values (for the elements where no certified numbers are available) in two SRMs were statistically indistinguishable. Also, the contents of 28 elements in candidate NIST SRM 1573a Tomato Leaves are reported. The EDXRF results were statistically indistinguishable from certified values for eight out of nine elements in NIST SRM 3087. The detection limit for this method is around at 0.1 μg cm -2 per element, so in BCR CRM No. 128, which is intended for ambient air pollution data, only Fe and Zn out of 14 elements reported in the certificate were detected with acceptable precision (i.e., 10%) owing to the very low air particulate matter loading, lying in the region of only 250 μg cm -2 . (Author)

Thermogravimetric and Differential Scanning Calorimetric Behavior of Ball-Milled Nuclear Graphite

Energy Technology Data Exchange (ETDEWEB)

Kim, Eung Seon; Kim, Min Hwan; Kim, Yong Wan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Yi Hyun; Cho, Seung Yon [National Fusion Research Institute, Daejeon (Korea, Republic of)

2013-10-15

An examination was made to characterize the oxidation behavior of ball-milled nuclear graphite powder through a TG-DSC analysis. With the ball milling time, the BET surface area increased with the reduction of particle size, but decreased with the chemisorptions of O{sub 2} on the activated surface. The enhancement of the oxidation after the ball milling is attributed to both increases in the specific surface area and atomic scale defects in the graphite structure. In a high temperature gas-cooled reactor, nuclear graphite has been widely used as fuel elements, moderator or reflector blocks, and core support structures owing to its excellent moderating power, mechanical properties and machinability. For the same reason, it will be used in a helium cooled ceramic reflector test blanket module for the ITER. Each submodule has a seven-layer breeding zone, including three neutron multiplier layers packed with beryllium pebbles, three lithium ceramic pebbles packed tritium breeder layers, and a reflector layer packed with 1 mm diameter graphite pebbles to reduce the volume of beryllium. The abrasion of graphite structures owing to relative motion or thermal cycle during operation may produce graphite dust. It is expected that graphite dust will be more oxidative than bulk graphite, and thus the oxidation behavior of graphite dust must be examined to analyze the safety of the reactors during an air ingress accident. In this study, the thermal stability of ball-milled graphite powder was investigated using a simultaneous thermogravimeter-differential scanning calorimeter.

Anti-seismic analysis for air storage tank used in the nuclear power plant

International Nuclear Information System (INIS)

Hua Jun; Ren Xin; Feng Ping

2011-01-01

This text calculates and analyses the structure of the air storage tank used for the SBO diesel generator set of Taishan nuclear power plant through finite element method, and simply introduces the mechanical modeling, loading condition and seismic response spectrum analyzing method for the structure, then get the natural frequency, vibration mode and response under seismic load of the structure through calculation. Evaluate the stress under the combined load such as gravity, internal stress, earthquake of the structure according to RCCM. The result shows that the structure intensity of the air storage tank meets the requirements of the specification. The calculating result gives the accordance for the seismic design of the air storage tank. (authors)

Silencing of dedicator of cytokinesis (DOCK180) obliterates pregnancy by interfering with decidualization due to blockage of nuclear entry of autoimmune regulator (AIRE).

Science.gov (United States)

Mohan, Jasna Jagan; Narayan, Prashanth; Padmanabhan, Renjini Ambika; Joseph, Selin; Kumar, Pradeep G; Laloraya, Malini

2018-03-08

Dedicator of cytokinesis (DOCK 180) involved in cytoskeletal reorganization is primarily a cytosolic molecule. It is recently shown to be nuclear in HeLa cells but its nuclear function is not known. The spatiotemporal distribution of DOCK180 in uterus was studied in uterine cytoplasmic and nuclear compartments during the "window of implantation." The functional significance of nuclear DOCK180 was explored by homology modeling, co-immunoprecipitation assays, and mass spectrometric analysis. Dock180's role in early pregnancy was ascertained by Dock 180 silencing and subsequent quantitative real-time PCR and Western blotting analysis. Our study shows a nuclear DOCK180 in the uterus during "window of implantation." Estrogen and progesterone mediate expression and nuclear translocation of DOCK180. The nuclear function of DOCK180 is attributed to its ability to import autoimmune regulator (AIRE) into the nucleus. Silencing of Dock180 inhibited AIRE nuclear shuttling which influenced its downstream targets, thereby affecting decidualization with AIRE and HOXA-10 as the major players as well as lack of implantation site formation due to impact on angiogenesis-associated genes. DOCK180 has an indispensable role in pregnancy establishment as knocking down Dock180 abrogates pregnancy by a consolidated impact on decidualization and angiogenesis by regulating AIRE nuclear entry. © 2018 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

Annular air space effects on nuclear waste canister temperatures in a deep geologic waste repository

International Nuclear Information System (INIS)

Lowry, W.E.; Cheung, H.; Davis, B.W.

1980-01-01

Air spaces in a deep geologic repository for nuclear high level waste will have an important effect on the long-term performance of the waste package. The important temperature effects of an annular air gap surrounding a high level waste canister are determined through 3-D numerical modeling. Air gap properties and parameters specifically analyzed and presented are the air gap size, surfaces emissivity, presence of a sleeve, and initial thermal power generation rate; particular emphasis was placed on determining the effect of these variables have on the canister surface temperature. Finally a discussion based on modeling results is presented which specifically relates the results to NRC regulatory considerations

Contaminant ingress into multizone buildings: An analytical state-space approach

KAUST Repository

Parker, Simon

2013-08-13

The ingress of exterior contaminants into buildings is often assessed by treating the building interior as a single well-mixed space. Multizone modelling provides an alternative way of representing buildings that can estimate concentration time series in different internal locations. A state-space approach is adopted to represent the concentration dynamics within multizone buildings. Analysis based on this approach is used to demonstrate that the exposure in every interior location is limited to the exterior exposure in the absence of removal mechanisms. Estimates are also developed for the short term maximum concentration and exposure in a multizone building in response to a step-change in concentration. These have considerable potential for practical use. The analytical development is demonstrated using a simple two-zone building with an inner zone and a range of existing multizone models of residential buildings. Quantitative measures are provided of the standard deviation of concentration and exposure within a range of residential multizone buildings. Ratios of the maximum short term concentrations and exposures to single zone building estimates are also provided for the same buildings. © 2013 Tsinghua University Press and Springer-Verlag Berlin Heidelberg.

Phase I aging assessment of nuclear air-treatment system high efficiency particulate air and adsorbers

International Nuclear Information System (INIS)

Winegardner, W.K.

1996-01-01

A phase I aging assessment of high efficiency particulate air filters and activated carbon gas adsorption units was performed by the Pacific Northwest Laboratory as part of the US Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. Information was compiled concerning design features, failure experience, aging mechanisms, effects, and stressors, and monitoring methods. Over 1100 failures, or 12% of the filter installations, were reported as part of a US Department of energy survey. Investigators from other laboratories have suggested that aging could have contributed to over 80% of these failures. Several instances of impaired performance as the result of the premature aging of carbon were reported. Filter aging mechanisms range from those associated with particle loading to reactions that alter the properties of gaskets. Mechanisms that can lead to impaired adsorber performance include the loss of potentially available active sites as a result of the adsorption of moisture or pollutants. Stressors include heat, moisture, radiation, and airborne particles and contaminants. (orig.)

Air toxics evaluation for a nuclear power plant

International Nuclear Information System (INIS)

Lokey, D.; Orr, W.

1994-01-01

An emission inventory of nonradiological hazardous air pollutants (HAP) was prepared for TVA's Browns Ferry Nuclear Plant (BFN). The purpose of this effort was to determine whether BFN is a major HAP emission source. About 40 specific HAP were identified in products used at FBN. HAP emission totals from BFN were estimated at 6 T/Y, well below the major-source cutoff. Off-site waste disposal reduced gross emission estimates by about 8 percent. HAP emission evaluation by product categories showed the largest portion due to paints and coatings, followed by cleaning compounds. HAP emission breakdown by chemical species showed xylene to be the predominate HAP emitted, followed by methyl ethyl ketone

Non-destructive vacuum decay method for pre-filled syringe closure integrity testing compared with dye ingress testing and high-voltage leak detection.

Science.gov (United States)

Simonetti, Andrea; Amari, Filippo

2015-01-01

solution, preventing possible prefilled syringe plunger movement during container closure integrity testing execution, is presented as well. The growing need to meet sterile drug products' regulatory, quality, and safety expectations has progressively driven new developments and improvements both in container closure integrity testing methods and in the respective equipment, over the last years. Indeed, container closure integrity testing establishes the container closure system capability to provide required protection to the drug product and to demonstrate maintenance of product sterility over its shelf life. This article describes the development of four container closure integrity testing approaches for the evaluation of glass prefilled syringe closure integrity, including two destructive (pharmacopoeial and Novartis specific dye ingress test) and two non-destructive (vacuum decay and high-voltage leak detection) methods. The important finding from the validation of comparative studies was that the vacuum decay method resulted in the most effective, reliable and repeatable detection of defective samples, whether the defect was exposed to sterile water, to drug product, or to air. Complete sets of known defects were created for this purpose (5 μm, 10 μm, 20 μm certified leakages by laser drilled holes and capillary tubes). All investigations and studies were conducted at Bonfiglioli Engineering S.r.l. (Vigarano Pieve, Ferrara, Italy) and at Novartis Vaccines (Sovicille, Siena, Italy). © PDA, Inc. 2015.

System approach for evaluation of air pollution toxic compounds in the 30-km area of nuclear power plants

International Nuclear Information System (INIS)

Shevtsova, O.V.; Zhigunova, L.N.; Makovskaya, N.A.; Pavlovich, E.L.

2012-01-01

The article shows the importance of a systematic approach to address environmental problems that arise during the construction of nuclear power plants, and identified the need to consider the transformation and biotransformation of primary pollutants and monitoring secondary pollutants. The basic pathways of pollutants in the air a 30-km zone of nuclear power plants established. The content of primary and secondary air pollutants identified. The evaluation of general toxic risk from primary pollutant and the calculation of the carcinogenic risk of secondary pollutants entering the body by inhalation are carried out. (authors)

Aging assessment of nuclear air-treatment system HEPA filters and adsorbers

International Nuclear Information System (INIS)

Winegardner, W.K.

1993-08-01

A Phase I aging assessment of high-efficiency particulate air (HEPA) filters and activated carbon gas adsorption units (adsorbers) was performed by the Pacific Northwest Laboratory (PNL) as part of the US Nuclear Regulatory Commission's (NRC) Nuclear Plant Aging Research (NPAR) Program. Information concerning design features; failure experience; aging mechanisms, effects, and stressors; and surveillance and monitoring methods for these key air-treatment system components was compiled. Over 1100 failures, or 12 percent of the filter installations, were reported as part of a Department of Energy (DOE) survey. Investigators from other national laboratories have suggested that aging effects could have contributed to over 80 percent of these failures. Tensile strength tests on aged filter media specimens indicated a decrease in strength. Filter aging mechanisms range from those associated with particle loading to reactions that alter properties of sealants and gaskets. Low radioiodine decontamination factors associated with the Three Mile Island (TMI) accident were attributed to the premature aging of the carbon in the adsorbers. Mechanisms that can lead to impaired adsorber performance include oxidation as well as the loss of potentially available active sites as a result of the adsorption of pollutants. Stressors include heat, moisture, radiation, and airborne particles and contaminants

A Survey on the effective role of nuclear power plants in decreasing air pollution and its relevant hazards

International Nuclear Information System (INIS)

Mohammadi, A.

2008-01-01

Nowadays air pollution, consequent reduction of Ozone layer's thickness and increase of UV radiations are included as the hazardous phenomenon, which confronts mankind with fundamental challenges. Increase of population, use of high living standards together with the consumption of fossil fuels for generations of electrical energy have increases air pollution at the global. scale. According to the carried out studies carried out in the three latest decades, alteration of atmospheric gases such as Ozone, dioxide azoth, dioxide sulphur, dioxide carbon, Methane, monoxide carbon and hydrocarbons have caused the appearance of water and air new forms of pollutions all over the world the harmful side effects resulted from air pollution on the respiratory systems and other cordial and blood vessels are well documented. Due to the air and water uncommon pollutions resulted from fossil fuels consumptions, use of nuclear power plants as a safe option can prevent several pollutants such as gases, poisoning metals and suspended elements or downpour of acidic rains in environment. In this article, it is tried difficulties and hazardous results of air pollution and resulted from consumption of fossil fuels, and discusses the effective role of nuclear energy studies in reduction of such pollutions

Monitoring of the vegetable garden open air spinach and soil radioactivity in Beijing during the Japan Fukushima nuclear accident

International Nuclear Information System (INIS)

Zhou Qiang; Xu Cuihua; Tuo Fei; Zhang Jing; Li Wenhong; Zhang Qing; Zhang Weijun; Zhang Jianfeng; Su Xu

2012-01-01

Objective: To detect artificial radionuclide content in the spinach and soil in open air vegetable garden in Beijing during Fukushima nuclear accident and to study the radioactive contamination characteristics of the samples. Methods: 6 spinach samples and 3 soil samples in open air vegetable garden were obtained through continuously sampling. High-purity germanium (HPGe) γ spectrometry was used to analyze activity concentrations of artificial radionuclide 131 I etc in these samples. Results: Artificial radionuclide 131 I was detected in the 6 open air spinach samples. Artificial radionuclide 137 Cs was detected in 3 vegetable garden soil samples, trace amount of 131 I was detected in 1 open-air surface soil sample alone. Conclusions: Following the Fukushima nuclear accident, spinach in Beijing's open-air vegetable garden was slightly polluted by artificial radionuclide 131 I, with the highest values of pollution appeared around April 4, 2011, but it could not cause harm to human health. (authors)

Interactions of RuO4(g) with different surfaces in nuclear reactor containments

International Nuclear Information System (INIS)

Holm, J.; Glaenneskog, H.; Ekberg, C.

2008-07-01

During a severe nuclear reactor accident with air ingress, ruthenium in the form of RuO4 can be released from the nuclear fuel. Hence, it is important to investigate how the reactor containment is able to reduce the source term of ruthenium. This work has investigated the distribution of RuO4 between an aqueous and gaseous phase in the temperature interval of 20-50 deg. C by on-line measurements with an experimental set-up made of glass. The experiments showed that RuO4 is almost immediately distributed in the aqueous phase after its introduction in the set-up in the entire temperature interval. However, the deposition of ruthenium on the glass surfaces in the system was significant. The speciation of the ruthenium on the glass surfaces was studied by SEM-EDX and ESCA and was determined to be the expected RuO2. Experiments of interactions between gaseous ruthenium tetroxide and the metals aluminium, copper and zinc have been investigated. The metals were treated by RuO4 (g) at room temperature and analyzed with ESCA, SEM and XRD. The analyses show that the black ruthenium deposits on the metal surfaces were RuO2, i.e. the RuO4 (g) has been transformed on the metal surfaces to RuO2(s). The analyses showed also that there was a significant deposition of ruthenium tetroxide especially on the copper and zinc samples. Aluminium has a lower ability to deposit gaseous ruthenium tetroxide than the other metals. The conclusion that can be made from the results is that surfaces in nuclear reactor containments will likely reduce the source term in the case of a severe accident in a nuclear power plant. (au)

Off-gas and air cleaning systems for accident conditions in nuclear power plants

International Nuclear Information System (INIS)

1993-01-01

This report surveys the design principles and strategies for mitigating the consequences of abnormal events in nuclear power plants by the use of air cleaning systems. Equipment intended for use in design basis accident and severe accident conditions is reviewed, with reference to designs used in IAEA Member States. 93 refs, 48 figs, 23 tabs

Intensity of the absorbing dose of the gamma rays in the air of Krusevac during and after nuclear accident in Chernobil

International Nuclear Information System (INIS)

Fortuna, D.

1997-01-01

In this paper are compared overage daily values of the intensity of the absorbing doses of the gamma rays in the air of Krusevac, during and after nuclear accident in Cernobil. Average daily values of intensity of the absorbing doses of gamma rays in the air of Krusevac, immediately after nuclear accident in Cernobil were, three to seven time higher than of the average daily values of the natural rays. (author)

Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-6 test data report: thermal hydraulic results, Rev. 0

International Nuclear Information System (INIS)

Lomperski, S.; Farmer, M.T.; Kilsdonk, D.; Aeschlimann, B.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure? (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼ φ 30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength is being addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus measures the fracture strength of the crust while it is either at room temperature or above, the latter state being achieved with a heating element placed below the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the sixth water ingression test, designated SSWICS-6. This test investigated

Design and safety aspects of nuclear district heating reactors

International Nuclear Information System (INIS)

Brogli, R.; Mathews, D.; Pelloni, S.

1989-01-01

Extensive studies on the rationale, the potential and the technology of nuclear district heating have been performed in Switzerland. Beside economics the safety aspects were of primary importance. Due to the high costs to transport heat the heating reactor tend to be small and therefore, minimally staffed and located close to population centers. Stringed safety rules are therefore applying. Gas cooled reactors are well suited as district heating reactors since they have due to their characteristics several inherent features, significant safety margins and a remarkable radioactivity retention potential. Some ways to mitigate the effects of water ingress and graphite corrosion are under investigation. (author). 5 refs, 3 figs

Design of off-gas and air cleaning systems at nuclear power plants

International Nuclear Information System (INIS)

1987-01-01

The primary purpose of this report is to describe the current design of air and process off-gas cleaning technologies used in nuclear power plants (NPPs). Because of the large inventory of fission products that are produced in the fuel (i.e. in the range of 5x10 19 Bq per GW(e)·a) and the highly restrictive airborne radionuclide release limits being established by Member States, air and process off-gas cleaning technologies are constantly being improved to provide higher airborne radionuclide recovery efficiencies and a smaller probability of malfunction. For various technologies considered an attempt has been made to provide the following information: (a) Process description in terms of principles of off-gas and air cleaning, operating parameters and system performance; (b) Design for normal and accident situations; (c) Design of components with regard to construction materials, size, shape and geometry of the system, resistance to chemical and physical degradation from the operational environment, safety and quality assurance requirements

Recommended radiological air sampling and internal contamination control at nuclear power plants

International Nuclear Information System (INIS)

Rich, B.L.; Ritter, P.D.; Martz, D.E.

1984-01-01

It has long been recognized by the NRC Technical Staffs that estimating the quantity of radioactivity inhaled by an individual worker involved large uncertainties. General air samples usually produce concentrations lower than those in the workers Breathing Zone (BZ). NRC guides have recognized this problem by specifying air monitoring programs which sample the Breathing Zone or concentrations known to be higher than that actually inhaled. In addition the availability of suitable samplers to obtain BZ samples and the practicality of requiring their use was somewhat in question to the NRC technical staff. AN NRC development contract was issued to provide a detailed review of the technical aspects of the problems and recommendations for practical upgrade of federal guidance. This project accomplished a review of the nuclear industry experience and knowledge through a literature search, site visits to representative licensed facilities, telephone surveys of many others, laboratory testing of personal air samplers (lapel samplers) and aerosol diffusion experiments to verify key conclusions and assumptions

Application of transient ignition model to multi-canister (MCO) accident analysis

International Nuclear Information System (INIS)

Kummerer, M.

1996-01-01

The potential for ignition of spent nuclear fuel in a Multi-Canister Overpack (MCO) is examined. A transient model is applied to calculate the highest ambient gas temperature outside an MCO wall tube or shipping cask for which a stable temperature condition exists. This integral analysis couples reaction kinetics with a description of the MCO configuration, heat and mass transfer, and fission product phenomena. It thereby allows ignition theory to be applied to various complex scenarios, including MCO water loss accidents and dry MCO air ingression

Aging assessment of essential HVAC chillers used in nuclear power plants

International Nuclear Information System (INIS)

Blahnik, D.E.; Camp, T.W.

1996-09-01

The Pacific Northwest Laboratory conducted a comprehensive aging assessment of chillers used in the essential safety air-conditioning systems in nuclear power plants (NPPs). The chillers used, and air-conditioning systems served, vary in design from plant to plant. The review of operating experience indicated that chillers experience aging degradation and failures. The primary aging factors of concern for chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. The evaluation of Licensee Event Reports (LERs) indicated that about 38% of the failures were primarily related to aging, 55% were partially aging related, and 7% of the failures were unassignable. About 25% of the failures were primarily caused by human, design, procedure, and other errors. The large number of errors is probably directly related to the complexity of chillers and their interfacing systems. Nearly all of the LERs were the result of entering plant Technical Specification Limiting Condition for Operation (LCO) that initiated remedial actions like plant shutdown procedures. The trend for chiller-related LERs has stabilized at about 0.13 LERs per plant year since 1988. Carefully following the vendor procedures and monitoring the equipment can help to minimize and/or eliminate most of the premature failures. Recording equipment performance can be useful for trending analysis. Periodic operation for a few hours on a weekly or monthly basis is useful to remove moisture and non-condensable gases that gradually build up inside the chiller. Chiller pressurization kits are available that will help minimize the amount of moisture and air ingress to low-pressure chillers during standby periods. The assessment of service life condition monitoring of chillers indicated there are many simple to sophisticated methods available that can help in chiller surveillance and monitoring

Aging assessment of essential HVAC chillers used in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Blahnik, D.E.; Camp, T.W.

1996-09-01

The Pacific Northwest Laboratory conducted a comprehensive aging assessment of chillers used in the essential safety air-conditioning systems in nuclear power plants (NPPs). The chillers used, and air-conditioning systems served, vary in design from plant to plant. The review of operating experience indicated that chillers experience aging degradation and failures. The primary aging factors of concern for chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. The evaluation of Licensee Event Reports (LERs) indicated that about 38% of the failures were primarily related to aging, 55% were partially aging related, and 7% of the failures were unassignable. About 25% of the failures were primarily caused by human, design, procedure, and other errors. The large number of errors is probably directly related to the complexity of chillers and their interfacing systems. Nearly all of the LERs were the result of entering plant Technical Specification Limiting Condition for Operation (LCO) that initiated remedial actions like plant shutdown procedures. The trend for chiller-related LERs has stabilized at about 0.13 LERs per plant year since 1988. Carefully following the vendor procedures and monitoring the equipment can help to minimize and/or eliminate most of the premature failures. Recording equipment performance can be useful for trending analysis. Periodic operation for a few hours on a weekly or monthly basis is useful to remove moisture and non-condensable gases that gradually build up inside the chiller. Chiller pressurization kits are available that will help minimize the amount of moisture and air ingress to low-pressure chillers during standby periods. The assessment of service life condition monitoring of chillers indicated there are many simple to sophisticated methods available that can help in chiller surveillance and monitoring.

Development of a non-radiological air emissions inventory for a nuclear industrial facility

International Nuclear Information System (INIS)

Patnoe, C.A.; Porter, G.V.; Almquist, R.S.

1991-01-01

This paper describes the major issues that impacted the organization and structure of a project for developing a comprehensive non- radiological air emissions inventory for a nuclear weapons facility. The major issues addressed paralleled the development of the inventory project and fall into the following categories: (1) defining the scope of work, (2) developing and managing the air emission inventory project, and (3) field investigations and evaluating operations for air emissions. This paper also describes the lines of communication that were established with state regulators to resolve problems and develop a successful working relationship. This paper illustrates a means to complete a complex air emission inventory with proper organization and cooperation with regulatory agencies. Further, it indicates the need of critical evaluation of project tasks to evaluate their impact on project schedule; it provides a method for implementing a quality assurance program that audits all phases of the emission survey; and it demonstrates a way of effectively managing outside contractors to meet schedule requirements and assure a high quality product. This paper is of value to those undertaking a similar complex air emission survey. 2 refs

Contamination mechanisms of air basin with tritium in venues of underground nuclear explosions at the former Semipalatinsk test site

International Nuclear Information System (INIS)

Lyakhova, O.N.; Lukashenko, S.N.; Larionova, N.V.; Tur, Y.S.

2012-01-01

During the period of testing from 1945 to 1962 at the territory of Semipalatinsk test site (STS) within the Degelen Mountains in tunnels, 209 underground nuclear explosions were produced. Many of the tunnels have seasonal water seepage in the form of streams, through which tritium migrates from the underground nuclear explosion (UNE) venues towards the surface. The issue of tritium contamination occupies a special place in the radioactive contamination of the environment. In this paper we assess the level and distribution of tritium in the atmospheric air of ecosystems with water seepage at tunnels № 176 and № 177, located on “Degelen” site. There has been presented general nature of tritium distribution in the atmosphere relative to surface of a watercourse which has been contaminated with tritium. The basic mechanisms were studied for tritium distribution in the air of studied ecosystems, namely, the distribution of tritium in the systems: water–atmosphere, tunnel air–atmosphere, soil water–atmosphere, vegetation–atmosphere. An analytical calculation of tritium concentration in the atmosphere by the concentration of tritium in water has been performed. There has experimentally obtained the dependence for predictive assessment of tritium concentrations in air as a function of tritium concentration in one of the inlet sources such as water, tunnel air, soil water, vegetation, etc.. The paper also describes the general nature of tritium distribution in the air in the area “Degelen”. - Highlights: ► The basic mechanisms for tritium distribution in the air of nuclear testing sites were examined. ► We researched the distribution of tritium in the systems such as water–atmosphere, tunnel air–atmosphere, soil water–atmosphere and vegetation–atmosphere. ► An analytical calculation of tritium concentration in the atmosphere was performed. ► We experimentally obtained the dependence for predictive assessment of tritium concentrations in

Use of nuclear and related analytical techniques in environmental research as exemplified by selected air pollution studies

International Nuclear Information System (INIS)

Smodis, B.; Jacimovic, R.; Jeran, Z.; Stropnik, B.; Svetina, M.

2000-01-01

Among nuclear and nuclear related analytical techniques, neutron activation analysis and X-ray fluorescence spectrometry proved to be particularly useful for environmental studies owing to their nondestructive character and multi element capability. This paper emphasizes their importance among other multielement analytical methods by discussing their specific role due to specific physics basis, quite different to other destructive non-nuclear methods, and by summarizing results obtained in several studies related to air pollution research, including analyses of airborne particulate matter, water samples, lichens and mosses. (author)

Dry air oxidation kinetics of K-Basin spent nuclear fuel

International Nuclear Information System (INIS)

Abrefah, J.; Buchanan, H.C.; Gerry, W.M.; Gray, W.J.; Marschman, S.C.

1998-06-01

The safety and process analyses of the proposed Integrated Process Strategy (IPS) to move the N-Reactor spent nuclear fuel (SNF) stored at K-Basin to an interim storage facility require information about the oxidation behavior of the metallic uranium. Limited experiments have been performed on the oxidation reaction of SNF samples taken from an N-Reactor outer fuel element in various atmospheres. This report discusses studies on the oxidation behavior of SNF using two independent experimental systems: (1) a tube furnace with a flowing gas mixture of 2% oxygen/98% argon; and (2) a thermogravimetric system for dry air oxidation

5 CFR 842.405 - Air traffic controllers, firefighters, law enforcement officers, and nuclear materials couriers.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 2 2010-01-01 2010-01-01 false Air traffic controllers, firefighters, law enforcement officers, and nuclear materials couriers. 842.405 Section 842.405 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT (CONTINUED) CIVIL SERVICE REGULATIONS (CONTINUED) FEDERAL EMPLOYEES RETIREMENT SYSTEM-BASIC ANNUITY Computations ...

Initial assessment of environmental effects on SiC/SiC composites in helium-cooled nuclear systems

Energy Technology Data Exchange (ETDEWEB)

Contescu, Cristian I [ORNL

2013-09-01

This report summarized the information available in the literature on the chemical reactivity of SiC/SiC composites and of their components in contact with the helium coolant used in HTGR, VHTR and GFR designs. In normal operation conditions, ultra-high purity helium will have chemically controlled impurities (water, oxygen, carbon dioxide, carbon monoxide, methane, hydrogen) that will create a slightly oxidizing gas environment. Little is known from direct experiments on the reactivity of third generation (nuclear grade) SiC/SiC composites in contact with low concentrations of water or oxygen in inert gas, at high temperature. However, there is ample information about the oxidation in dry and moist air of SiC/SiC composites at high temperatures. This information is reviewed first in the next chapters. The emphasis is places on the improvement in material oxidation, thermal, and mechanical properties during three stages of development of SiC fibers and at least two stages of development of the fiber/matrix interphase. The chemical stability of SiC/SiC composites in contact with oxygen or steam at temperatures that may develop in off-normal reactor conditions supports the conclusion that most advanced composites (also known as nuclear grade SiC/SiC composites) have the chemical resistance that would allow them maintain mechanical properties at temperatures up to 1200 1300 oC in the extreme conditions of an air or water ingress accident scenario. Further research is needed to assess the long-term stability of advanced SiC/SiC composites in inert gas (helium) in presence of very low concentrations (traces) of water and oxygen at the temperatures of normal operation of helium-cooled reactors. Another aspect that needs to be investigated is the effect of fast neutron irradiation on the oxidation stability of advanced SiC/SiC composites in normal operation conditions.

Testing of adsorbents used in nuclear power plant air cleaning systems using the open-quotes Newclose quotes standards

International Nuclear Information System (INIS)

Freeman, W.P.

1993-01-01

Ever since the publication of the NRC Information Notice No. 87-32: Deficiencies in the Testing of Nuclear-Grade Activated Charcoal, nuclear power facilities in the US have struggled in their efforts to open-quotes...review the information for applicability to their facilities and consider action, if appropriate ...close quotes as stated in the notice. The encouragement of resident NRC inspectors at some nuclear power facilities has prompted a variety of responses ranging from no change at all in testing requirements to contemplated changes in plant technical specifications. This confusion is the result of a couple factors. The first factor is the lack of a current revision to NRC Regulatory Guide 1.52, the basic document used in nuclear power plant technical specifications for the testing of engineered-safety feature (ESF) post accident air cleaning systems. The second factor is the standards that have been written since the last revision of Reg. Guide 1.52 which include two revision of ANSI N509 and N510, two revisions of RDT M16-1T, two version of ASTM D3803, two versions of ASTM D4069, and three versions of an SME code AG-1. Few of the standards and codes listed above are commensurate with each other and, thus, present a nearly insolvable maze to the HVAC engineer asked to upgrade adsorbent testing requirements following the standards. This paper describes the authors experience with a number of nuclear power facilities in their efforts to meet the requirements of the new standards of testing adsorbents from nuclear power plant air cleaning systems. The existing standards are discussed in light of the current state of the art for adsorbent testing of adsorbent media from nuclear air treatment systems. Test results are presented showing the impact of new test requirements on acceptance criteria when compared to the old test requirements and recommendations are offered for solution of this testing problem in the future. 12 refs., 5 tabs

Roles of texture in controlling oxidation, hydrogen ingress and hydride formation in Zr alloys

International Nuclear Information System (INIS)

Szpunar, Jerzy A.; Qin, Wen; Li, Hualong; Kumar, Kiran

2011-01-01

Experimental observations shows that the oxide formed on Zr alloys are strongly textured. The texture and grain-boundary characteristics of oxide are dependent on the texture of metal substrate. Computer simulation and thermodynamic modeling clarify the effect of metal substrate on structure of oxide film, and intrinsic factors affecting the microstructure. Models of diffusion process of hydrogen atoms and oxygen diffusion through oxide are presented. Both intra-granular and inter-granular hydrides were found following (0001) α-Zr //(111) δ-ZrH1.5 relationship. The through-thickness texture inhomogeneity in cladding tubes, the effects of hoop stress on the hydride orientation and the formation of interlinked hydride structure were studied. A thermodynamic model was developed to analyze the nucleation and the stress-induced reorientation of intergranular hydrides. These works provide a framework for understanding the oxidation, the hydrogen ingress and the hydride formation in Zr alloys. (author)

Features of adsorbed chemical elements and their isotopes distribution in iodine air filters AU-1500 of nuclear power plant

International Nuclear Information System (INIS)

Neklyudov, I.M.; Dovbnya, A.N.; Dikiy, N.P.; Ledenyov, O.P.; Lyashko, Yu.V.

2013-01-01

The main aim of research is to investigate the physical features of spatial distribution of the adsorbed chemical elements and their isotopes in the granular filtering medium in the iodine air filters of the type of AU-1500 in the forced-exhaust ventilation at the nuclear power plant. The ?-activation analysis method is applied to accurately characterize the distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the AU-1500 iodine air filter after its long term operation at the nuclear power plant. The typical spectrum of the detected chemical elements and their isotopes in the AU-1500 iodine air filter, which was exposed by the irradiation of bremsstrahlung gamma-quantum producing by the accelerating electrons in the tantalum target, are obtained. The spatial distributions of the detected chemical element 127 I and some other chemical elements and their isotopes in the layer of absorber, which was made of the cylindrical coal granules of the type of SKT-3, in the AU-1500 iodine air filter are also researched. The possible influences by the standing wave of air pressure in the iodine air filter on the spatial distribution of the chemical elements and their isotopes in the iodine air filter are discussed. The comprehensive analysis of obtained research results on the distribution of the adsorbed chemical elements and their isotopes in the absorber of iodine air filter is performed.

Aging and service wear of air compressors and dryers in nuclear power plants

International Nuclear Information System (INIS)

Moyers, J.C.

1989-01-01

Compressed air systems and their associated compressors and dryers as incorporated in LWR power plants usually are not classified as safety related systems and components because their continued operation is not required to bring the plant to a safe shutdown condition. However, control air is a vital requirement for maintaining stable plant operation and its loss often results in a reactor trip and, on occasion, the actuation of engineered safety feature systems. Concerns caused by repeated instances of failures in air systems resulted in the high-priority ranking of Generic Issue No. 43, ''Reliability of Air Systems'' by the NRC. In support of the Nuclear Plant Aging Research (NPAR) Program, the Oak Ridge National Laboratory is carrying out a Phase I aging assessment of air compressors and dryers used in LWR power plants. The objectives of this study include: (1) determination of the types and ratings of equipment utilized in typical plants; (2) identification of aging and service wear stressors imposed on the machines; (3) evaluation of operating experience with the machines; (4) comparison of user and manufacturer-recommended inspection, surveillance, and monitoring (ISM) methods; and (5) the identification of any improved ISM methods that might lead to longer, more reliable, service. 2 refs

Subcritical wet air oxidation of organic solvents and chelating agents of the nuclear fuel

International Nuclear Information System (INIS)

Bachir, Souley

1999-01-01

This document deals with the environment control, more specially organic solvents and chelating agents destruction, employed in the nuclear industry. This work details the subcritical wet air oxidation process. Another part of the document deals with the possible coupling between this process and the biodegradation technic in the framework of the sewage sludges treatment. (A.L.B.)

Source term estimation for small sized HTRs

International Nuclear Information System (INIS)

Moormann, R.

1992-08-01

Accidents which have to be considered are core heat-up, reactivity transients, water of air ingress and primary circuit depressurization. The main effort of this paper belongs to water/air ingress and depressurization, which requires consideration of fission product plateout under normal operation conditions; for the latter it is clearly shown, that absorption (penetration) mechanisms are much less important than assumed sometimes in the past. Source term estimation procedures for core heat-up events are shortly reviewed; reactivity transients are apparently covered by them. Besides a general literature survey including identification of areas with insufficient knowledge this paper contains some estimations on the thermomechanical behaviour of fission products in water in air ingress accidents. Typical source term examples are also presented. In an appendix, evaluations of the AVR experiments VAMPYR-I and -II with respect to plateout and fission product filter efficiency are outlined and used for a validation step of the new plateout code SPATRA. (orig.)

Safe-air view: a decision support system for nuclear emergencies

International Nuclear Information System (INIS)

Triacchini, G.; D'Alberti, F.; Canepa, E.

2004-01-01

It was therefore necessary to implement a PC based software for the prediction of the radiological impact on the environment and on the population around the JRC Ispra site caused by any accident occurring at any nuclear facilities within the site. For this reason the SSRP unit has developed with other partners a specific decision PC based support tool, whose characteristics are described in this paper. The developed SW is the first implementation of GIS technology applied to an existing MS-DOS trademark model validated model for wind field definition, calculation of atmospheric dispersion and concentration of pollutants at receptors. The software has been designed as to be able to superimpose, for each point in an area of 50 km radius from the JRC Ispra, layers of information coming from customisable databases. The result is a user-friendly Windows trademark based software, able to quickly calculate and display values of ground and air radioactive contamination around JRC Ispra, following an accidental release of radioactive substances from within a JRC Ispra nuclear installation. (orig.)

Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release

International Nuclear Information System (INIS)

Desgranges, L.

2006-12-01

After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO 2 oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO 2 to U 3 O 7 , and from U 3 O 7 to U 3 O 8 ), and with further high activity laboratory experiments

The use of CFD code for numerical simulation study on the air/water countercurrent flow limitation in nuclear reactors

International Nuclear Information System (INIS)

Morghi, Youssef; Mesquita, Amir Zacarias; Santos, Andre Augusto Campagnole dos; Vasconcelos, Victor

2015-01-01

For the experimental study on the air/water countercurrent flow limitation in Nuclear Reactors, were built at CDTN an acrylic test sections with the same geometric shape of 'hot leg' of a Pressurized Water Reactor (PWR). The hydraulic circuit is designed to be used with air and water at pressures near to atmospheric and ambient temperature. Due to the complexity of the CCFL experimental, the numerical simulation has been used. The aim of the numerical simulations is the validation of experimental data. It is a global trend, the use of computational fluid dynamics (CFD) modeling and prediction of physical phenomena related to heat transfer in nuclear reactors. The most used CFD codes are: FLUENT®, STAR- CD®, Open Foam® and CFX®. In CFD, closure models are required that must be validated, especially if they are to be applied to nuclear reactor safety. The Thermal- Hydraulics Laboratory of CDTN offers computing infrastructure and license to use commercial code CFX®. This article describes a review about CCFL and the use of CFD for numerical simulation of this phenomenal for Nuclear Rector. (author)

The use of CFD code for numerical simulation study on the air/water countercurrent flow limitation in nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Morghi, Youssef; Mesquita, Amir Zacarias; Santos, Andre Augusto Campagnole dos; Vasconcelos, Victor, E-mail: ymo@cdtn.br, E-mail: amir@cdtn.br, E-mail: aacs@cdtn.br, E-mail: vitors@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

For the experimental study on the air/water countercurrent flow limitation in Nuclear Reactors, were built at CDTN an acrylic test sections with the same geometric shape of 'hot leg' of a Pressurized Water Reactor (PWR). The hydraulic circuit is designed to be used with air and water at pressures near to atmospheric and ambient temperature. Due to the complexity of the CCFL experimental, the numerical simulation has been used. The aim of the numerical simulations is the validation of experimental data. It is a global trend, the use of computational fluid dynamics (CFD) modeling and prediction of physical phenomena related to heat transfer in nuclear reactors. The most used CFD codes are: FLUENT®, STAR- CD®, Open Foam® and CFX®. In CFD, closure models are required that must be validated, especially if they are to be applied to nuclear reactor safety. The Thermal- Hydraulics Laboratory of CDTN offers computing infrastructure and license to use commercial code CFX®. This article describes a review about CCFL and the use of CFD for numerical simulation of this phenomenal for Nuclear Rector. (author)

Impact of Air Entraining Method on the Resistance of Concrete to Internal Cracking

Science.gov (United States)

Wawrzeńczyk, Jerzy; Molendowska, Agnieszka

2017-10-01

This paper presents the test results of air entrained concrete mixtures made at a constant W/C ratio of 0.44. Three different air entraining agents were used: polymer microspheres, glass microspheres and a conventional air entraining admixture. The aim of this study was to compare the effectiveness of the air entraining methods. Concrete mixture tests were performed for consistency (slump test), density and, in the case of AEA series, air content by pressure method. Hardened concrete tests were performed for compressive strength, water absorption, resistance to chloride ingress, and freeze-thaw durability - resistance to internal cracking tests were conducted in accordance with PN-88/B-06250 on cube specimens and with the modified ASTM C666 A test method on beam specimens; porosity characteristics (A, A300, \\bar L) were determined to PN-EN 480-11:1998. No significant mass and length changes were recorded for the concrete air entrained with the conventional methods or with polymer microspheres. The results indicate that polymer microspheres are a very good alternative to traditional air entraining methods for concrete, providing effective air entrainment and protection from freezing and thawing. The glass microsphere-based concretes showed insufficient freeze-thaw resistance. The test results indicate that both the conventional methods (AEA) and the air entrainment by polymer microspheres are effective air entraining methods. It has to be noted that in the case of the use of polymer microspheres, a comparable value of \\bar L and a very good freeze-thaw resistance can be achieved at a noticeably lower air and micropore contents and at lower strength loss.

Extended-life nuclear air cleaning filters via dynamic exclusion prefilters

Energy Technology Data Exchange (ETDEWEB)

Wright, S.R.; Crouch, H.S.; Bond, J.H. [Micro Composite Materials Corp., Durham, NC (United States)

1997-08-01

The primary objective of this investigation was to ascertain if a dynamic, self-cleaning particulate exclusion precleaner, designed for relatively large dust removal (2 to 100+ {mu}m diameter particles) from helicopter turbine inlets, could be extended to submicron filtration. The improved device could be used as a prefilter for HEPA filtration systems, significantly increasing service life. In nuclear air cleaning, its use would reduce the amount of nuclear particulate matter that would otherwise be entrapped in the HEPA filter cartridge/panel, causing fouling and increased back pressure, as well as requiring subsequent disposal of the contaminated media at considerable expense. A unique (patent-pending) mechanical separation device has recently been developed to extract particulate matter from fluid process streams based on a proprietary concept called Boundary Layer Momentum Transfer (BLMT). The device creates multiple boundary layers that actively exclude particles from entering the perimeter of the device, while allowing air to traverse the boundaries relatively unimpeded. A modified two-dimensional (2-D) computerized flow simulation model was used to assist in the prototype design. Empirical results are presented from particle breakthrough and AP experiments obtained from a reduced-scale prototype filter. Particles larger than 0.23 {mu}m were actively excluded by the prototype, but at a higher pressure drop than anticipated. Experimental data collected indicates that the filter housing and the inlet flow configuration may contribute significantly to improvements in device particle separation capabilities. Furthermore, preliminary experiments have shown that other downstream pressure drop considerations (besides those just across the spinning filtration disks) must be included to accurately portray the AP across the device. Further detailed quantitative investigations on a larger scale (1,000 CFM) prototype are warranted. 3 refs., 5 figs., 2 tabs.

Pollution of atmospheric air with toxic and radioactive particulate matter investigated by means of nuclear techniques

International Nuclear Information System (INIS)

Jagielak, J.

1978-01-01

The application of spectrometric methods of nuclear techniques to the investigations of atmospheric air pollution by toxic and radioactive elements and results of these investigations conducted in the highly industrialized and urbanized regions of Poland have been presented. The method of precipitation of the samples, the measurements and analysis of radiation spectra of alpha and gamma radiation emitted by isotopes present in the samples have been described. The concentrations of toxic metal dust in the air have been evaluated by neutron activation and X-ray fluorescence analysis. Appropriate methods of measurement, calibration of instrument and the discussion of results have been presented. The work presents the results of investigations performed in Siersza within the years 1973-1974 and in Warsaw in the period of 1975-1977, which have permitted to estimate the mean monthly values of concentration in the atmospheric air of the following radioisotopes: 7 Be, 54 Mn, 95 Zr, 103 Ru, 106 Ru, 125 Sb, 131 I, 137 Cs, 140 Ba, 141 Ce, 144 Ce, 226 Ra, Th-nat, U-nat and the following stable elements: Sc, Cr, Fe, Co, Zn, As, Se, Sb, W, Pb. The analysis of changes in concentration of each particular artificial radioisotope in the air for the region of Poland in connection with Chinese nuclear explosions have been given. On the basis of the performed environmental investigations the method of analysis of relations between the concentrations of particular elements present in the dust has been discussed. The applications of this method have been presented. The hazard to the population and the environment caused by the radioactive and toxic dust present in the atmospheric air has been estimated. (author)

Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System

Energy Technology Data Exchange (ETDEWEB)

Stenner, Robert D.; Hadley, Donald L.; Armstrong, Peter R.; Buck, John W.; Hoopes, Bonnie L.; Janus, Michael C.

2001-03-01

Indoor air quality effects on human health are of increasing concern to public health agencies and building owners. The prevention and treatment of 'sick building' syndrome and the spread of air-borne diseases in hospitals, for example, are well known priorities. However, increasing attention is being directed to the vulnerability of our public buildings/places, public security and national defense facilities to terrorist attack or the accidental release of air-borne biological pathogens, harmful chemicals, or radioactive contaminants. The Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System (IA-NBC-HMAS) was developed to serve as a health impact analysis tool for use in addressing these concerns. The overall goal was to develop a user-friendly fully functional prototype Health Modeling and Assessment system, which will operate under the PNNL FRAMES system for ease of use and to maximize its integration with other modeling and assessment capabilities accessible within the FRAMES system (e.g., ambient air fate and transport models, water borne fate and transport models, Physiologically Based Pharmacokinetic models, etc.). The prototype IA-NBC-HMAS is designed to serve as a functional Health Modeling and Assessment system that can be easily tailored to meet specific building analysis needs of a customer. The prototype system was developed and tested using an actual building (i.e., the Churchville Building located at the Aberdeen Proving Ground) and release scenario (i.e., the release and measurement of tracer materials within the building) to ensure realism and practicality in the design and development of the prototype system. A user-friendly "demo" accompanies this report to allow the reader the opportunity for a "hands on" review of the prototype system's capability.

Contamination mechanisms of air basin with tritium in venues of underground nuclear explosions at the former Semipalatinsk test site.

Science.gov (United States)

Lyakhova, O N; Lukashenko, S N; Larionova, N V; Tur, Y S

2012-11-01

During the period of testing from 1945 to 1962 at the territory of Semipalatinsk test site (STS) within the Degelen Mountains in tunnels, 209 underground nuclear explosions were produced. Many of the tunnels have seasonal water seepage in the form of streams, through which tritium migrates from the underground nuclear explosion (UNE) venues towards the surface. The issue of tritium contamination occupies a special place in the radioactive contamination of the environment. In this paper we assess the level and distribution of tritium in the atmospheric air of ecosystems with water seepage at tunnels № 176 and № 177, located on "Degelen" site. There has been presented general nature of tritium distribution in the atmosphere relative to surface of a watercourse which has been contaminated with tritium. The basic mechanisms were studied for tritium distribution in the air of studied ecosystems, namely, the distribution of tritium in the systems: water-atmosphere, tunnel air-atmosphere, soil water-atmosphere, vegetation-atmosphere. An analytical calculation of tritium concentration in the atmosphere by the concentration of tritium in water has been performed. There has experimentally obtained the dependence for predictive assessment of tritium concentrations in air as a function of tritium concentration in one of the inlet sources such as water, tunnel air, soil water, vegetation, etc.. The paper also describes the general nature of tritium distribution in the air in the area "Degelen". Copyright © 2012 Elsevier Ltd. All rights reserved.

Air particulate pollution studies in Asian countries using nuclear analytical techniques

International Nuclear Information System (INIS)

Hien, P.D.

1998-01-01

Air particulate pollution is regarded as critical in Asian cities. The levels of suspended particulate matter in major Asian cities far exceed the WHO's guideline. Nuclear analytical techniques have been widely used in the studies of air particulate pollution to provide aerosol elemental compositions for the purpose of deriving the structure of emission sources. This paper presents some preliminary observations and findings based on publications in scientific literatures. Data on PM-10 levels and socio-economic indicators are used for searching a relationship between air quality and the level of development across Asia. An inverse linear relationship between PM-10 levels and logarithm of per capita GDP appears to exist, although there are large fluctuations of data caused by the very different climatic and geographical conditions of cities studied. Soil dust is generally a major, or even predominant aerosol source in Asian cities. Other common sources include vehicular emissions, coal and oil combustion, burning of refuse (in open) and biomass (including forest fires). The relevance and the trends of these sources in Asian context are discussed. Multivariate receptor modelling techniques applied in source characterization are illustrated through the cases of Lahore and Hochiminh City. Although having limitations in dealing with mixing and overlapping sources, receptor modelling based on principal component factor analysis has been proven to be uncomplicated and sufficiently reliable for characterising aerosol sources in urban areas. (author)

Effects of porosity and temperature on oxidation behavior in air of selected nuclear graphites

International Nuclear Information System (INIS)

Chen Dongyue; Li Zhengcao; Miao Wei; Zhang Zhengjun

2012-01-01

Nuclear graphite endures gas oxidation in High Temperature Gas-cooled Reactor (HTGR), which may threaten the safety of reactor. To study the oxidation behavior of nuclear graphite, weight loss curve is usually measured through Thermo Gravimetric Analysis (TGA) method. In this work, three brands of nuclear graphite for HTGR (i.e., HSM-SC, IG-11, and NBG-18) are oxidized under 873 and 1073 K in open air, and their weight loss curves are obtained. The acceleration of oxidizing rate is observed for both HSM-SC and IG-11, and is attributed to the large porosity increase during oxidation process. For HSM-SC, the porosity increase comes from preferential binder oxidation, and thus its binder quality shall be improved to obtain better oxidation resistance. Temperature effects on oxidation for HSM-SC are also studied, which shows that oxidizing gas tends to be exhausted at graphite surface at high temperature instead of penetrate into the interior of bulk. (author)

Air oxidation of Zircaloy-4 in the 600-1000 °C temperature range: Modeling for ASTEC code application

Science.gov (United States)

Coindreau, O.; Duriez, C.; Ederli, S.

2010-10-01

Progress in the treatment of air oxidation of zirconium in severe accident (SA) codes are required for a reliable analysis of severe accidents involving air ingress. Air oxidation of zirconium can actually lead to accelerated core degradation and increased fission product release, especially for the highly-radiotoxic ruthenium. This paper presents a model to simulate air oxidation kinetics of Zircaloy-4 in the 600-1000 °C temperature range. It is based on available experimental data, including separate-effect experiments performed at IRSN and at Forschungszentrum Karlsruhe. The kinetic transition, named "breakaway", from a diffusion-controlled regime to an accelerated oxidation is taken into account in the modeling via a critical mass gain parameter. The progressive propagation of the locally initiated breakaway is modeled by a linear increase in oxidation rate with time. Finally, when breakaway propagation is completed, the oxidation rate stabilizes and the kinetics is modeled by a linear law. This new modeling is integrated in the severe accident code ASTEC, jointly developed by IRSN and GRS. Model predictions and experimental data from thermogravimetric results show good agreement for different air flow rates and for slow temperature transient conditions.

Large eddy simulation of Loss of Vacuum Accident in STARDUST facility

International Nuclear Information System (INIS)

Benedetti, Miriam; Gaudio, Pasquale; Lupelli, Ivan; Malizia, Andrea; Porfiri, Maria Teresa; Richetta, Maria

2013-01-01

Highlights: ► Fusion safety, plasma material interaction. ► Numerical and experimental data comparison to analyze the consequences of Loss of Vacuum Accident that can provoke dust mobilization inside the Vacuum Vessel of the Nuclear Fusion Reactor ITER-like. -- Abstract: The development of computational fluid dynamic (CFD) models of air ingress into the vacuum vessel (VV) represents an important issue concerning the safety analysis of nuclear fusion devices, in particular in the field of dust mobilization. The present work deals with the large eddy simulations (LES) of fluid dynamic fields during a vessel filling at near vacuum conditions to support the safety study of Loss of Vacuum Accidents (LOVA) events triggered by air income. The model's results are compared to the experimental data provided by STARDUST facility at different pressurization rates (100 Pa/s, 300 Pa/s and 500 Pa/s). Simulation's results compare favorably with experimental data, demonstrating the possibility of implementing LES in large vacuum systems as tokamaks

Determination of the radioiodine species in the exhaust air of nuclear facilities

International Nuclear Information System (INIS)

Birke, G.; Deuber, H.

1977-01-01

In the stack exhaust air of the nuclear power stations the portion of inorganic 131 I was, apart from 2 sampling periods, less than 50%. In the stack exhaust air of the research reactor the inorganic 131 I prevailed. The removal efficiency of the I 2 sorption materials DSM 11 and DSM 17 for 131 I in the form of CH 3 I and C 6 H 5 I was very low. 131 I in the form of C 6 H 5 I was removed by AC 6120 and LMS 13 X-Ag (Linde molecular sieve in the Ag form) to a very small extent too, by activated charcoal impregnated with KI or TEDA however to a very high extent. In the experiments concerning the preparation and removal of 131 I in the form of HIO an iodine species that was difficult to remove with AC 6120 was found which could be HIO. Its maximum portion in the carrier gas was 50%. (orig./RW) [de

Crew Configuration, Ingress/Egress Procedures, and In-Flight Caregiving Capacity in a Space Ambulance Based on the Boeing X-37B

Science.gov (United States)

Halberg, Ephriam Etan

This study proposes that a Boeing X-37B space plane, its dimensions and performance characteristics estimated from publicly available documents, diagrams, and photographs, could be internally redesigned as a medical evacuation (ambulance) vehicle for the International Space Station. As of 2017, there is currently no spacecraft designed to accommodate a contingency medical evacuation wherein a crew member aboard the ISS is injured or ailing and must be returned to Earth for immediate medical attention. The X-37B is an unmanned vehicle with a history of success in both sub-orbital testing and all four of its long-duration orbital missions to date. Research conducted at UC Davis suggests that it is possible to retain the outer mold line of the X-37B while expanding the internal payload compartment to a volume sufficient for a crew of three--pilot, crew medical officer, and injured crew member--throughout ISS un-dock and atmospheric entry, descent, and landing. In addition to crew life support systems, this re-purposed X-37B, hereafter referred to as the X-37SA (Space Ambulance), includes medical equipment for stabilization of a patient in-transit. This study suggests an optimal, ergonomic crew configuration and berthing port location, procedures for microgravity ingress and 1G egress, a minimum medical equipment list and location within the crew cabin for the medical care and monitoring equipment. Conceptual crew configuration, ingress/egress procedures, and patient/equipment access are validated via physical simulation in a full-scale mockup of the proposed X-37SA crew cabin.

Development of an air cleaning system for dissolving high explosives from nuclear warheads

Energy Technology Data Exchange (ETDEWEB)

Bergman, W.; Wilson, K.; Staggs, K.; Wapman, D. [Lawrence Livermore National Lab., CA (United States)

1997-08-01

The Department of Energy (DOE) has a major effort underway in dismantling nuclear weapons. In support of this effort we have been developing a workstation for removing the high explosive (HE) from nuclear warheads using hot sprays of dimethyl sulfoxide (DMSO) solvent to dissolve the HE. An important component of the workstation is the air cleaning system that is used to contain DMSO aerosols and vapor and radioactive aerosols. The air cleaning system consists of a condenser to liquefy the hot DMSO vapor, a demister pad to remove most of the DMSO aerosols, a high efficiency particulate air (HEPA) filter to remove the remaining aerosols, an activated carbon filter to remove the DMSO vapor, and a final HEPA filter to meet the redundancy requirement for HEPA filters in radioactive applications. The demister pad is a 4{double_prime} thick mat of glass and steel fibers and was selected after conducting screening tests on promising candidates. We also conducted screening tests on various activated carbons and found that all had a similar performance. The carbon breakthrough curves were fitted to a modified Wheeler`s equation and gave excellent predictions for the effect of different flow rates. After all of the components were assembled, we ran a series of performance tests on the components and system to determine the particle capture efficiency as a function of size for dioctyl sebacate (DOS) and DMSO aerosols using laser particle counters and filter samples. The pad had an efficiency greater than 990% for 0.1 {mu}m DMSO particles. Test results on the prototype carbon filter showed only 70% efficiency, instead of the 99.9% in small scale laboratory tests. Thus further work will be required to develop the prototype carbon filter. 7 refs., 18 figs., 10 tabs.

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

Energy Technology Data Exchange (ETDEWEB)

Thornton, G.; Rothstein, A.J.

1962-06-28

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

On possibilities to decrease influence of oxidation processes on oil yield at oil shale retorting

International Nuclear Information System (INIS)

Yefimov, V.; Loeoeper, R.; Doilov, S.; Kundel, H.

1993-01-01

At the present technical level retorting is carried out so that an increase in specific air consumption results in an increase of oxygen ingress into the semi coking shaft. At the same time a direct relationship between the degree of volatiles pyrolysis and specific air consumption was observed. This regularity enables to assume that within the reaction volume there occurs most likely the thermo oxidative pyrolysis of volatile products, not the oxidation of oil shale as it is considered traditionally. The main source of oxygen ingress ed into the semi coking shaft at processing oil shale in retorts is the process of spent shale. This process is not fully elaborated for utilization in commercial scale and can not be arranged so that the ingress of oxygen into the smacking chamber could be eliminated. In case of a slower semi coke gasification process and reduced specific air consumption for gasification the absolute amount of oxygen ingress ed into the semi coking shaft also decreases. One of the efficient methods to decrease specific air consumption is to build furnaces into the semi coking chamber to obtain additional amount of heat carrier by combusting generator gas. The maximum effect is reached when steam-and-air blow is completely replaced by recycle gas: specific air consumption is reduced whereas recycle gas is deoxygenated in the cooling zone while passing through spent shale bed which has the temperature of about 500 deg C. Another possible source of oxygen to the semi coking shaft with heat carrier is production of flue gases by combusting recycle gas in burners built in retorts. We consider the recycle gas employed upon processing oil shale in retorts hardly to be an appreciable source of the oxygen ingress into the semi coking shaft. Additional amounts of residual oxygen containing in recycle gas fed into both cooling zone and furnaces are practically totally consumed at gas combusting and passing across the bed of semi coke heated up to approximately

OECM MCCI Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-2 final data report, Rev. 0 February 12, 2003

International Nuclear Information System (INIS)

Lomperski, S.; Farmer, M.T.; Kilsdonk, D.; Aeschlimann, B.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼φ30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the second water ingression test, designated SSWICS-2. The test investigated the quench behavior of a 15 cm deep, fully

Compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the Federal Republic of Germany in 1975

International Nuclear Information System (INIS)

Winkelmann, I.; Endrulat, H.J.; Haubelt, R.; Westpfahl, U.

1976-04-01

The present compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the FRG is a continuation of a report series on aerosol filter and iodine filter samples from the exhaust air control systems of the nuclear power plants Gundremmingen, Obrigheim, Wuergassen, Stade, Lingen and Biblis A. The reports have been issued by the Federal public health office since 1972. This report is supplemented by annual release values on radioactive noble gases, on short- and long-lived aerosols, and on gaseous 131 I, supplied by the individual nuclear power plants as in previous years on uniform questionnaires. Data on the release of tritium are also available from some nuclear power plants. (orig.) [de

Air Oxidation Behaviors of Zircaloy-4 Cladding During a LOCA In Spent Fuel Pool

International Nuclear Information System (INIS)

Bang, Je Geon; Chun, Tae Hyun; Kim, Sun Ki; Koo, Yang Hyun

2014-01-01

It is well known that air oxidation induces a serious degradation of the Zircaloy cladding material, compared with steam oxidation. From the oxidant point of view, in comparison with steam, chemical heat release during oxidation in air is higher by 80%, which may lead to a more rapid degradation of the Zircaloy cladding, and further evolution of the accident.. Additionally, the oxidation kinetics in air is much faster than in steam due to the formation of non-protective oxide layer. From the safety point of view, the barrier effect of the cladding against release of fission products is lost much earlier in air compared to steam. The objective of this study is to investigate the oxidation behaviors of fuel cladding in two different conditions such as isothermal and transient condition and to generate its kinetic data under an accident condition in the spent fuel pool. In this study, the oxidation behaviors and its kinetics of the Zircaloy-4 were investigated in air environment for various air ingress scenarios in the temperature range 600 .deg. C-1,400 .deg. C by thermo-gravimetric analysis. In this study, the oxidation behaviors of the Zircaloy-4 for both isothermal condition and transient condition were investigated in air environment. In comparison with isothermal condition, the retardation of oxidation rate in transient condition was observed at both 1,200 .deg. C and 1,400 .deg. C. This seems to be ascribed to the effect of thin oxide formed during a heating

Unit for air decontamination; Unidad para descontaminacion de aire

Energy Technology Data Exchange (ETDEWEB)

Mariano H, E

1991-02-15

To fulfill the applicable requirements of safety to the ventilation systems in nuclear facilities, it is necessary to make a cleaning of the air that hurtles to the atmosphere. For that which was designed and it manufactured an unit for decontamination of the air for the Pilot plant of production of Nuclear Fuel that this built one with national parts, uses Hepa national filters and the design can adapt for different dimensions of filters, also can be added a lodging for a prefilter or to adopt two Hepa filters. (Author)

OECD MCCI project Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-1 test data report: thermal hydraulic results. Rev. 0 September 20, 2002

International Nuclear Information System (INIS)

Lomperski, S.; Farmer, M.T.; Kilsdonk, D.J.; Aeschlimann, R.W.; Basu, S.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼φ30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the first water ingression test, designated SSWICS-1. The report includes a description of the test apparatus, the

Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core

International Nuclear Information System (INIS)

Smith, O.L.

1992-01-01

Accidental admission of moisture into the primary system of a Modular High-Temperature Gas-Cooled Reactor (MHTGR) has been identified in US Department of Energy-sponsored studies as an important safety concern. The work described here develops an analytical methodology to quantify the pressure and reactivity consequences of steam-generator tube rupture and other moistureingress-related incidents. Important neutronic and thermohydraulic processes are coupled with reactivity feedback and safety and control system responses. Rate and magnitude of steam buildup are found to be dominated by major system features such as break size in comparison with safety valve capacity and reliability, while being less sensitive to factors such as heat transfer coefficients. The results indicate that ingress transients progress at a slower pace than previously predicted by bounding analyses, with milder power overshoots and more time for operator or automatic corrective actions

Coupling of RELAP5-3D and GAMMA codes for Nuclear Hydrogen System Analysis

International Nuclear Information System (INIS)

Jin, Hyung Gon

2007-02-01

RELAP5-3D is one of the most important system analysis codes in nuclear field, which has been developed for best-estimate transient simulation of light water reactor coolant systems during postulated accidents. The GAMMA code is a multi-dimensional multi-component mixture analysis code with the complete set of chemical reaction models which is developed for safety analysis of HTGR (High Temperature Gas Cooled Reactor) air-ingress. The two codes, RELAP5-3D and GAMMA, are coupled to be used for nuclear-hydrogen system analysis, which requires the capability of the analysis of multi-component gas mixture and two-phase flow. In order to couple the two codes, 4 steps are needed. Before coupling, the GAMMA code was transformed into DLL (dynamic link liberally) from executive type and RELAP5-3D was recompiled into Compaq Visual Fortran environments for our debugging purpose. As the second step, two programs - RELAP5-3D and GAMMA codes - must be synchronized in terms of time and time step. Based on that time coupling, the coupled code can calculate simultaneously. Time-step coupling had been accomplished successfully and it is tested by using a simple test input. As a next step, source-term coupling was done and it was also tested in two different test inputs. The fist case is a simple test condition, which has no chemical reaction. And the other test set is the chemical reaction model, including four non-condensable gas species, which are He, O2, CO, CO2. Finally, in order to analyze combined cycle system, heat-flux coupling has been made and a simple heat exchanger model was demonstrated

Safety implications of a graphite oxidation accident in the compact ignition tokamak device

International Nuclear Information System (INIS)

Merrill, B.J.; O'Brien, M.H.

1989-01-01

This paper addresses the possible safety consequences of an air ingress accident for the Compact Ignition Tokamak (CIT) device. An experimental program was undertaken to determine oxidation rates of four nuclear grade graphites in air at temperatures ranging from 800 to 1800 C and flow velocities from 3 to 7 m/s. On the basis of these test results, an analytic model was developed to assess the extent of first wall/divertor protective tile oxidation and the amount of energy released from this oxidation. For CIT, a significant restriction to vacuum vessel air inflow will be provided by the air seals and walls of the surrounding test cells. Under these conditions, the graphite oxidation reaction inside the vacuum vessel will become oxygen starved within minutes of the onset of this event. Since significant oxidation rates were not achieved, the heat release did not elevate structural temperatures to levels of concern with regard to activated material release. 7 refs., 9 figs

Aging of control and service air compressors and dryers used in nuclear power plants

International Nuclear Information System (INIS)

Moyers, J.C.

1990-07-01

This report was produced under the Detection of Defects and Degradation Monitoring of Nuclear Plant Safety Equipment element of the Nuclear Plant Aging Research Program. This element includes the identification of practical and cost-effective methods for detecting, monitoring, and assessing the severity of time-dependent degradation (aging) of control and service air compressors and dryers in nuclear power plants. These methods are to provide capabilities for establishing degradation trends prior to failure and developing guidance for effective maintenance. The topics of this Phase 1 assessment report are failure modes and causes resulting from aging, manufacturer--recommended maintenance and surveillance practices, and measurable parameters (including functional indicators) for use in assessing operational readiness, establishing degradation trends, and detecting incipient failure. the results presented are based on information derived from operating experience records, manufacturer-supplied information, and input from plant operators. For each failure mode, failure causes are listed by subcomponent, and parameters potentially useful for detecting degradation that could lead to failure are identified. 13 refs., 9 figs., 16 tabs

Analysing the Air: Experiences and Results of Long Term Air Pollution Monitoring in the Asia-Pacific Region Using Nuclear Analysis Techniques

International Nuclear Information System (INIS)

Atanacio, Armand J.

2015-01-01

Particles present in the air we breathe are now recognized as a major cause of disease and premature death globally. In fact, a World Health Organization (WHO) report recently ranked ambient air pollution as one of the top 10 causes of death in the world, directly contributing annually to around 3.7 million premature deaths worldwide 65% of which occurred in the Asian region alone. Airborne particulate matter (PM) can be generated from natural sources such as windblown soil or coastal sea-spray; as well as anthropogenic sources such as power stations, industry, vehicles and domestic biomass burning. At low concentration these fine pollution particles are too small to be seen by eye, but penetrate deep into our lungs and even our blood stream as our nose and throat are inefficient at filtering them out. At large concentrations, they can also have wider regional effects including reduced visibility, acid rain and even climate variability. The International Atomic Energy Agency (IAEA) in 2000, recognizing air pollution as a significant local, national and global challenge, initiated a collaborative air pollution study involving 14 countries across the greater Asia-pacific region from 2000 to 2015. This has amassed a database containing more than 14,000 data lines of PM mass concentration and the concentration of up to 40 elements using nuclear analytical techniques. It represents the most comprehensive and long-term airborne PM data set compiled to date for the Asia-Pacific region and as will be discussed, can be used to statistically resolve individual source fingerprints and their contributions to total air pollution using Positive Matrix Factorization (PMF). This sort of data necessary for implementing or reviewing the effectiveness of policy level changes aimed at targeted air pollution reduction. (author)

Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1

International Nuclear Information System (INIS)

Fernandez-Moguel, Leticia

2015-01-01

Highlights: • The PSI air oxidation model has been successfully implemented in MELCOR. • The model treats oxygen as an active species and nitrogen as a catalyst. • The implementation has been assessed against the previous post-test analyses for QUENCH-16. • The pre-oxidation and air phase were consistent when similar modelling options were used. • All code versions were in fair agreement with the experimental data. - Abstract: The PSI air oxidation model has been successfully implemented in the lump parameter code MELCOR. The PSI air oxidation model treats oxygen as an active species and nitrogen as a catalyst that accelerates the oxidation kinetics. The essential feature of the model is the transition from parabolic to linear kinetics. The implementation has been assessed against the previous post-test analyses for the air ingress experiment QUENCH-16 performed with a local version of RELAP5/SCDAPSim3.5. This version contains the PSI air oxidation model. The pre-oxidation and air phase were consistent when similar modelling options were used and all code versions were in fair agreement with the experimental data, showing consistency in the implementation of the model. The PSI air oxidation model will be used in the future for analysis of spent fuel pool uncovery sequences where steam/air mixture is the prototypical environment

An assessment of air sampling location for stack monitoring in nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Bok [University of Science and Technology, Daejeon (Korea, Republic of); Kim, Tae Hyoung; Lee, Jong Il; Kim, Bong Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-06-15

In this study, air sampling locations in the stack of the Advanced Fuel Science Building (AFSB) at the Korea Atomic Energy Research Institute (KAERI) were assessed according to the ANSI/HPS N13.1-1999 specification. The velocity profile, flow angle and 10 μm aerosol particle profile at the cross-section as functions of stack height L and stack diameter D (L/D) were assessed according to the sampling location criteria using COMSOL. The criteria for the velocity profile were found to be met at 5 L/D or more for the height, and the criteria for the average flow angle were met at all locations through this assessment. The criteria for the particle profile were met at 5 L/D and 9 L/D. However, the particle profile at the cross-section of each sampling location was found to be non-uniform. In order to establish uniformity of the particle profile, a static mixer and a perimeter ring were modeled, after which the degrees of effectiveness of these components were compared. Modeling using the static mixer indicated that the sampling locations that met the criteria for the particle profile were 5-10 L/D. When modeling using the perimeter ring, the sampling locations that met the criteria for particle profile were 5 L/D and 7-10 L/D. The criteria for the velocity profile and the average flow angle were also met at the sampling locations that met the criteria for the particle profile. The methodologies used in this study can also be applied during assessments of air sampling locations when monitoring stacks at new nuclear facilities as well as existing nuclear facilities.

Nuclear propulsion apparatus with alternate reactor segments

International Nuclear Information System (INIS)

Szekely, T.

1979-01-01

Nuclear propulsion apparatus comprising: (a) means for compressing incoming air; (b) nuclear fission reactor means for heating said air; (c) means for expanding a portion of the heated air to drive said compressing means; (d) said nuclear fission reactor means being divided into a plurality of radially extending segments; (e) means for directing a portion of the compressed air for heating through alternate segments of said reactor means and another portion of the compressed air for heating through the remaining segments of said reactor means; and (f) means for further expanding the heated air from said drive means and the remaining heated air from said reactor means through nozzle means to effect reactive thrust on said apparatus. 12 claims

Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 2

International Nuclear Information System (INIS)

Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

1993-08-01

The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 1

International Nuclear Information System (INIS)

Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

1993-08-01

The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

OECD MCCI Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-3 test data report: thermal Hydraulic results, Rev. 0 February 19, 2003

International Nuclear Information System (INIS)

Lomperski, S.; Farmer, M.T.; Kilsdonk, D.; Aeschlimann, B.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼φ30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the third water ingression test, designated SSWICS-3. This test investigated the quenching behavior of a fully oxidized PWR

Air lock

International Nuclear Information System (INIS)

Palkovich, P.; Gruber, J.; Madlener, W.

1974-01-01

The patent refers to an air lock system preferably for nuclear stations for the transport of heavy loads by means of a trolley on rails. For opening and closing of the air lock parts of the rails are removed, e.g. by a second rail system perpendicular to the main rails. (P.K.)

Dynamic in vivo mapping of model moisturiser ingress into human skin by GARfield MRI.

Science.gov (United States)

Ciampi, Elisabetta; van Ginkel, Michael; McDonald, Peter J; Pitts, Simon; Bonnist, Eleanor Y M; Singleton, Scott; Williamson, Ann-Marie

2011-02-01

We describe the development of in vivo one-dimensional MRI (profiling) using a GARField (Gradient At Right angles to Field) magnet for the characterisation of side-of-hand human skin. For the first time and in vivo, we report measurements of the NMR longitudinal and transverse relaxation parameters and self-diffusivity of the upper layers of human skin with a nominal spatial resolution better than 10 µm. The results are correlated with in vivo confocal Raman spectroscopy measurements of water concentration and natural moisturiser factors, and discussed in terms of known skin biology and microstructure of the stratum corneum and viable epidermis. The application of model moisturiser solutions to the skin is followed and their dynamics of ingress are characterised using the MRI methodology developed. Selected hydrophilic and lipophilic formulations are studied. The results are corroborated by standard in vivo measurements of transepidermal water loss and hydration status. A further insight into moisturisation mechanisms is gained. The effect of two different penetration enhancers on a commonly used skin care oil is also discussed, and different timescales of oil penetration into the skin are reported depending on the type of enhancer. Copyright © 2010 John Wiley & Sons, Ltd.

Unusual occurrences during the whole operation of BN-250 NPP

International Nuclear Information System (INIS)

Andropenkov, S.

2000-01-01

Unusual occurrences during the whole operation BN-350 NPP. 1. Oil ingress in high pressure receiver for the not reveled reason, 12.05.1994. 2. lncrease of water radioactivity of circulating water supply system due to heat exchanger leak of spent fuel assembly washing out system, 17.09.1993. 3. Lack of passableness of sodium drain header of primary circuit reveled during inspection on scheduled preventative maintenance, 28.11.1996. 4. Destruction of the blow-off line of MCP-6 due to corrosion damage of the pipeline while unit was being operated at rated power, 23.04.1993. 5. Lack of passableness of blow-down pipeline connecting reactor gas cover with gas-type pressurizer while unit was being operated at rated power, 17.11.1994. 6. Sodium ingress in blow-down pipeline of loop-5 intermediate heat exchanger while loop-5 was being fed of sodium during scheduled preventative maintenance, 27.06.1994. 7. Resistance deterioration of electro heating zones of loop-4 due to heat exchanger leak and water ingress in air-pipeline of primary circuit boxes recirculating air system, 02.05.1997. 8. Resistance deterioration of electro heating zones of sodium drain header of secondary circuit was sopped in the water for the extinguishing the fire of blowing ventilation oil-strainer, 23.12.1994. 9. Sodium ingress in gas-type pressurizer through pipeline of primary sodium cleanup system and blow-down pipeline of failed MCP-2 while primary sodium cleanup system was being connected to the primary circuit, 17.08.1976. As a rule, the main reactor systems are scrutinized more carefully than the auxiliary reactor systems and the order actions are existed for eliminating and mitigating of consequences of main reactor system fails. Therefore the auxiliary reactor system fails may impact on the main reactor systems through places of its contact in significant measure. The influence of auxiliary reactor system fails on main reactor systems and its possible consequences for behavior of the main

Fuel elements and safety engineering goals

International Nuclear Information System (INIS)

Schulten, R.; Bonnenberg, H.

1990-01-01

There are good prospects for silicon carbide anti-corrosion coatings on fuel elements to be realised, which opens up the chance to reduce the safety engineering requirements to the suitable design and safe performance of the ceramic fuel element. Another possibility offered is combined-cycle operation with high efficiencies, and thus good economic prospects, as with this design concept combining gas and steam turbines, air ingress due to turbine malfunction is an incident that can be managed by the system. This development will allow economically efficient operation also of nuclear power reactors with relatively small output, and hence contribute to reducing CO 2 emissions. (orig./DG) [de

The Effects of Nuclear Weapons. Third edition

Energy Technology Data Exchange (ETDEWEB)

Glasstone, S; Dolan, P J

1977-01-01

Since the last edition of ''The Effects of Nuclear Weapons'' in 1962 much new information has become available concerning nuclear weapon effects. This has come in part from the series of atmospheric tests, including several at very high altitudes, conducted in the Pacific Ocean area in 1962. In addition, laboratory studies, theoretical calculations, and computer simulations have provided a better understanding of the various effects. A new chapter has been added on the electromagnetic pulse. The chapter titles are as follows: general principles of nuclear explosions; descriptions of nuclear explosions; air blast phenomena in air and surface bursts; air blast loading; structural damage from air blast; shock effects of surface and subsurface bursts; thermal radiation and its effects; initial nuclear radiation; residual nuclear radiation and fallout; radio and radar effects; the electromagnetic pulse and its effects; and biological effects. (LTN)

Preliminary assessment of the thermal effects of an annular air space surrounding an emplaced nuclear waste canister

International Nuclear Information System (INIS)

Davis, B.W.

1979-01-01

Modeling results have previously shown that the presence of a large air space (e.g., a repository room) within a nuclear waste repository is expected to cause a waste canister's temperature to remain cooler than it would otherwise be. Results presented herein show that an annular air space surrounding the waste canisters can have similar cooling effects under certain prescribable conditions; for a 16 ft x 1 ft diameter canister containing 650 PWR rods which initially generate a total of 4.61 kw, analysis will show that annular air spaces greater than 11 in will permit the canister surface to attain peak temperatures lower than that which would result from a zero-gap/perfect thermal contact. It was determined that the peak radial temperature gradient in the salt varies in proportion to the inverse of the drill hole radius. Thermal radiation is shown to be the dominant mode of heat transfer across an annular air space during the first two years after emplacement. Finally, a methodology is presented which will allow investigators to easily model radiation and convection heat transfer through air spaces by treating the space as a conduction element that possesses non-linear temperature dependent conductivity

Optimization in the nuclear fuel cycle II: Concentration of alpha emitters in the air

International Nuclear Information System (INIS)

Pereira, W.S.; Silva, A.X.; Lopes, J.M.; Carmo, A.S.; Mello, C.R.; Fernandes, T.S.; Kelecom, A.

2017-01-01

Optimization is one of the bases of radioprotection and aims to move doses away from the dose limit that is the borderline of acceptable radiological risk. The work aims to use the monitoring of the concentration of alpha emitters in the air as a tool of the optimization process. We analyzed 27 sampling points of airborne alpha concentration in a nuclear fuel cycle facility. The monthly averages were considered statistically different, the highest in the month of February and the lowest in the month of August. All other months were found to have identical mean activity concentration values. Regarding the sampling points, the points with the highest averages were points 12, 15 and 9. These points were indicated for the beginning of the optimization process. Analysis of the production of the facility should be performed to verify possible correlations between production and concentration of alpha emitters in the air

Fundamental study of a water jet injected into a vacuum vessel of fusion reactor under the ingress of coolant event

International Nuclear Information System (INIS)

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi; Kurihara, Ryouichi; Ueda, Shuzou

1996-01-01

As one of some transient sequences for the thermofluid safety in ITER, pressure rise and boiling heat transfer characteristics in a Tokamak vacuum vessel during an ingress of coolant event (ICE) are being investigated experimentally by using the preliminary ICE apparatus. The pressure rise rates in the vacuum vessel and the wall temperature distributions on the target plate were measured quantitatively and clarified at first. In addition, a two-phase flow under the ICE conditions was analyzed numerically for predicting the experimental results using one-dimensional transport equations and the drift-flux model. The experimental results were compared with the numerical results. It was found that the pressurization behavior during the ICE conditions could be estimated qualitatively by the present numerical analyses. 5 refs., 5 figs

Properties of aerosol floating in the air in a nuclear power plant workplace environment

International Nuclear Information System (INIS)

Karasawa, H.; Funabashi, M.; Ito, M.

1992-01-01

An investigation was carried out on properties of radioactive aerosol floating in the air at several workplaces in nuclear power plant. The principal results are as follows: the aerosol particle size distributions consisted of two particle groups, whose aerodynamic diameters ranged from 4 to 7 microns and from 0.4 to 0.6 microns; the radioactive aerosol particle size distribution were unimodal. The mean activity median aerodynamic diameter (AMAD) was 6 microns, with geometric standard deviation microns; and, the average density of the aerosol was about 2.2g/cm 3 . (author)

Air pollution, nuclear power and electricity demand: an economic perspective

International Nuclear Information System (INIS)

Chapman, D.; Mount, T.; Czerwinski, M.; Younger, M.

1983-09-01

We have studied the potential for physical or financial disruption of the electric utility system in New York as it may be affected by nuclear power availability, air pollution control policy, inflation, and economic growth. The method of analysis is the EPA-sponsored CCMU model which integrates utility economics, demand forecasting and customer charges, air pollution control, and power plant dispatching. The CCMU model is a partial version of the AUSM; the latter model is being developed to include coal supply and capacity planning. Of all the cases examined, only one type seems to create a severe crisis which leads to possible public reorganization of the industry. These are the cases in which the Shoreham and Nine Mile 2 plants are not operated, and 50% or more of the investment cost is not allowed in the rate base. In these circumstances, the state's utilities would apparently be unable to meet debt obligations and would also need to discontinue dividend payments. The extremity of this situation should be emphasized. These specific cases already assume that liability for debt and dividend payments has been shared equally over all of the state's utilities and customers. It assumes that the state's Power Pool has already implemented a plan by which the principal owners of the two plants are relieved of their principal financial and generating responsibilities. In all other cases studied, the statewide industry appears capable of managing the problems examined

Environmental planning and the siting of nuclear facilities: the integration of water, air, coastal, and comprehensive planning into the nuclear siting process. Improving regulatory effectiveness in federal/state siting actions

International Nuclear Information System (INIS)

Noble, J.B.; Epting, J.T.; Blumm, M.C.; Ackerman, S.; Laist, D.W.

1977-02-01

The National Environmental Policy Act, the Coastal Zone Management Act, the Federal Water Pollution Control Act, the Clean Air Act Amendments, and the Housing and Urban 701 Comprehensive Planning Assistance Program are discussed in relation to the planning and siting of nuclear facilities

Nuclear energy worldwide

International Nuclear Information System (INIS)

Fertel, M.

2000-01-01

In this short paper the author provides a list of tables and charts concerning the nuclear energy worldwide, the clean air benefits of nuclear energy, the nuclear competitiveness and the public opinion. He shows that the nuclear energy has a vital role to play in satisfying global energy and environmental goals. (A.L.B)

Counting systems characterization for air activity measurements

International Nuclear Information System (INIS)

Vijayakumar, B.; Balamurugan, M.; Ravi, P.M.

2018-01-01

Air activity measurements are carried out continuously at all the nuclear power plant (NPP) sites both during pre-operational phase and also during operation of nuclear facility. These measurements provide a trend line for the background air activity in the surrounding environments of an operating NPP. Any increase in air activity over the benchmark level becomes very handy to investigate the releases from the station and to give feedback to the operators of NPP about the prevailing air activity levels and their correlation to the plant releases. This paper compiles the results obtained for air filter samples using different counters operating in GM region and also plastic scintillators

Measurement of 131I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment.

Science.gov (United States)

Brudecki, K; Szczodry, A; Mróz, T; Kowalska, A; Mietelski, J W

2018-03-01

This paper presents results of 131 I air activity measurements performed within nuclear medical hospitals as a tool for internal dose assessment. The study was conducted at a place of preparation and administration of 131 I ("hot room") and at a nurse station. 131 I activity measurements were performed for 5 and 4 consecutive working days, at the "hot room" and nurse station, respectively. Iodine from the air was collected by a mobile HVS-30 aerosol sampler combined with a gas sampler. Both the gaseous and aerosol fractions were measurement. The activities in the gaseous fraction ranged from (28 ± 1 Bq m -3 ) to (492 ± 4) Bq m -3 . At both sampling sites, the activity of the gaseous iodine fraction trapped on activated charcoal was significantly higher than that of the aerosol fraction captured on Petrianov filter cloth. Based on these results, an attempt has been made to estimate annual inhalation effective doses, which were found to range from 0.47 mSv (nurse female) to 1.3 mSv (technician male). The highest annual inhalation equivalent doses have been found for thyroid as 32, 27, 13, and 11 mSv, respectively, for technician male, technical female, nurse male, and nurse female. The method presented here allows to fill the gaps in internal doses measurements. Moreover, because method has been successful used for many years in radioactive contamination monitoring of air in cases of serious nuclear accidents, it should also be used in nuclear medicine.

Autonomous urban reconnaissance ingress system (AURIS): providing a tactically relevant autonomous door-opening kit for unmanned ground vehicles

Science.gov (United States)

Shane, David J.; Rufo, Michael A.; Berkemeier, Matthew D.; Alberts, Joel A.

2012-06-01

The Autonomous Urban Reconnaissance Ingress System (AURIS™) addresses a significant limitation of current military and first responder robotics technology: the inability of reconnaissance robots to open doors. Leveraging user testing as a baseline, the program has derived specifications necessary for military personnel to open doors with fielded UGVs (Unmanned Ground Vehicles), and evaluates the technology's impact on operational mission areas: duration, timing, and user patience in developing a tactically relevant, safe, and effective system. Funding is provided through the US ARMY Tank Automotive Research, Development and Engineering Center (TARDEC) and the project represents a leap forward in perception, autonomy, robotic implements, and coordinated payload operation in UGVs. This paper describes high level details of specification generation, status of the last phase of development, an advanced view of the system autonomy capability, and a short look ahead towards the ongoing work on this compelling and important technology.

‹Portale›, die zum Nachdenken anregen. Einblicke in eine Interfaceanalyse des Augmented Reality Spiels Ingress

Directory of Open Access Journals (Sweden)

Franco Rau

2017-02-01

Full Text Available Augmented Reality Spiele wie ‹Ingress› und ‹PokémonGo› stellen aktuell neue mediale Phänomene dar. Eine zentrale Differenz zu klassischen Massively Multiplayer Online Games (MMOs ist die Verzahnung von virtuellen und realen Objekten als konstitutive Spielelemente. In Anknüpfung an die Perspektive, digitale Spiele als Kultur- und Bildungsräume zu verstehen, widmet sich der Beitrag der Frage, inwiefern das Ingress-Spielen die Perspektive von Spieler/innen auf den öffentlichen Raum verändern kann. In erster Annäherung an diese Fragestellung wird auf Basis einer Interfaceanalyse gezeigt, wie ‹Portale› – virtueller Repräsentationen realer Objekte im Spiel – potenziell Irritationen und Differenz­erfahrungen ermöglichen. Diese können zum Ausgangspunkt weiterführender Reflexionen werden. Dafür werden exemplarisch ‹Portale› diskutiert, die (1. weiterführende Informationen zu realen Objekte bieten, die (2. Momentaufnahmen nicht mehr existierender kultureller Objekte darstellen und die (3. reale Objekte in ironischer Weise präsentieren.

Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Vutchkov, Mitko

2001-01-01

The main goal of the Coordinated Research Project (No:9937/R0), entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear and Related Analytical Techniques', is to identify and validate site specific epiphytic plants for biomonitoring the atmospheric pollution in Jamaica using nuclear analytical techniques at the International Centre for Environmental and Nuclear Sciences (ICENS). The specific objectives for the second year of the project were: Development of HOP for sampling epiphytic plants in Jamaica; Sampling design and sample collection; Sample preparation and analysis; Development of an in-house SRM and participation in the NAT-5 inter-laboratory study; Data analysis and interpretation of the results; Development of a work plan of the third year of the project

OECD MMCI Small-Scale Water Ingression and Crust Strength tests (SSWICS) SSWICS-1 final data report, Rev. 1 February 10, 2003.; Report, Rev. 1

International Nuclear Information System (INIS)

Lomperski, S.; Farmer, M.T.; Kilsdonk, D.; Aeschlimann, B.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure; and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼φ30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the first water ingression test, designated SSWICS-1. The test investigated the quench behavior of a 15 cm deep, fully

Spent nuclear fuel storage vessel

International Nuclear Information System (INIS)

Watanabe, Yoshio; Kashiwagi, Eisuke; Sekikawa, Tsutomu.

1997-01-01

Containing tubes for containing spent nuclear fuels are arranged vertically in a chamber. Heat releasing fins are disposed horizontal to the outer circumference of the containing tubes for rectifying cooling air and promoting cooling of the containing tubes. Louvers and evaporation sides of heat pipes are disposed at a predetermined distance in the chamber. Cooling air flows from an air introduction port to the inside of the chamber and takes heat from the containing tubes incorporated with heat generating spent nuclear fuels, rising its temperature and flows off to an air exhaustion exit. The direction for the rectification plate of the louver is downward from a horizontal position while facing to the air exhaustion port. Since the evaporation sides of the heat pipes are disposed in the inside of the chamber and the condensation side of the heat pipes is disposed to the outside of the chamber, the thermal energy can be recovered from the containing tubes incorporated with spent nuclear fuels and utilized. (I.N.)

Copper Doping of Zinc Oxide by Nuclear Transmutation

Science.gov (United States)

2014-03-27

Copper Doping of Zinc Oxide by Nuclear Transmutation THESIS Matthew C. Recker, Captain, USAF AFIT-ENP-14-M-30 DEPARTMENT OF THE AIR FORCE AIR...NUCLEAR TRANSMUTATION THESIS Presented to the Faculty Department of Engineering Physics Graduate School of Engineering and Management Air Force...COPPER DOPING OF ZINC OXIDE BY NUCLEAR TRANSMUTATION Matthew C. Recker, BS Captain, USAF Approved: //signed// 27 February 2014 John W. McClory, PhD

Nuclear power

International Nuclear Information System (INIS)

Abd Khalik Wood

2005-01-01

This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

Unit for air decontamination

International Nuclear Information System (INIS)

Mariano H, E.

1991-02-01

To fulfill the applicable requirements of safety to the ventilation systems in nuclear facilities, it is necessary to make a cleaning of the air that hurtles to the atmosphere. For that which was designed and it manufactured an unit for decontamination of the air for the Pilot plant of production of Nuclear Fuel that this built one with national parts, uses Hepa national filters and the design can adapt for different dimensions of filters, also can be added a lodging for a prefilter or to adopt two Hepa filters. (Author)

Background air pollution studies in urban and rural areas of Bangladesh using nuclear-related analytical techniques

International Nuclear Information System (INIS)

Khan, A.H.; Khaliquzzaman, M.; Tarafdar, S.A.; Biswas, S.K.; Islam, A.

1994-01-01

The trace element constituents of aerosols such as Hg, Pb, Cd, Se, As, Cu, Zn, Cr, V, etc. are permanent pollutants affecting the biosphere and the general ecosystem. The measurements of these elements collected on air filters, in rainwater, and also in some bioindicators such as moss and lichen, can yield very significant information on the origin, transport, removal and deposition of these pollutants. A set of sensitive and precise nuclear-related and chemical methods such as PIXE, EDXRF, FAAS and DPASV have, therefore, been developed and applied to analyze a number of trace and minor elements in air particulates, coal fly ash, plant materials, moss and water. Further analytical developments would include INAA and TRXRF. Some of the results from air particulates (integral), coal fly ash and moss analyses are presented to illustrate the experience level of the Laboratory. A core programme of study on the trace element composition of aerosols from urban and rural atmosphere in Bangladesh has been planned for implementation within the framework of this CRP. 10 refs, 1 fig., 5 tabs

RadNet Radiological Air Monitoring Network

International Nuclear Information System (INIS)

Scott Telofski, J.; Askren, D.R.; Petko, Ch.M.; Fraass, R.G.

2010-01-01

The United States Environmental Protection Agency operates a national environmental radiation monitoring program called RadNet. RadNet monitors airborne particulates, precipitation, milk, and drinking water for radiation levels. The primary purpose of the original program in the 1950's and 1960's was to collect and analyze samples in various media to assess the effects of radioactive fallout from above-ground nuclear weapon testing. As above-ground testing diminished in the 1970's, the program, especially the air network, became critical in evaluating effects of other types of nuclear incidents, such as the nuclear reactor accident at Chernobyl, as well as monitoring trends in environmental radioactive contamination. The value of rapid data collection subsequent to such incidents led to the consideration of developing air monitors with radiation detectors and telecommunication equipment for real-time radiation measurement. The strengthened United States homeland security posture after 2001 led to production and installation of the current real-time RadNet air monitors. There are now 118 stationary, continuously operating air monitoring stations and 40 mobile air monitors for site specific monitoring. The stationary air monitors include radiation detectors, meteorological sensors, a high-volume air sampler, and communication devices for hourly data transfers. When unusual levels are detected, scientists download a full sodium iodide detector spectrum for analysis. The real-time data collected by RadNet stationary systems permit rapid identification and quantification of airborne nuclides with sufficient sensitivity to provide critical information to help determine protective actions. The data also may help to rapidly refine long-range radioactive plume models and estimate exposure to the population. This paper provides an overview of the airborne particulate monitoring conducted during above-ground nuclear weapon testing, summarizes the uses of data from the program

Nuclear law in progress; Derecho nuclear en evolución

Energy Technology Data Exchange (ETDEWEB)

Manóvil, Rafael Mariano [ed.

2014-07-01

The 21. AIDN / INLA Congress was organized by the International Nuclear Law Association, in Buenos Aires, between the October 20 and 23, 2014. In this event, were presented almost 50 papers about these subjects: radioactive sources, safety and licensing, radioactive waste management, radiation protection, nuclear transport, security and non-proliferation, nuclear liability and insurance, etc.

Dose factors to calculate the radiation exposure due to radioactive waste air from nuclear facilities

International Nuclear Information System (INIS)

Brenk, H.D.; Vogt, K.J.

1977-01-01

An evaluation of the environmental impact of nuclear plants according to paragraph 45 of the Radiation Protection Directive of the Federal Republic of Germany requires the calculation of dose conversion factors indicating the correlation between the contaminated medium and individual radiation exposure. The present study is to be conceived as a contribution to discussion on this subject. For the determination of radiation exposure caused by the waste air of nuclear plants, models are being specified for computing the dose conversion factors for the external exposure pathways of β-submersion, γ-submersion and γ-radiation from contaminated ground as well as the internal exposure pathways of inhalation and ingestion, which further elaborate and improve the models previously applied, especially as far as the ingestion pathway is concerned, which distinguishes between 6 major food categories. The computer models are applied to those radionuclides which are significan for nuclear emitters, in particular nuclear light-water power stations. The results obtained for the individual exposure pathways and affected organs are specified in the form of tables. For this purpose, calculations were first of all carried out for the so-called 'reference man'. The results can be transferred to population groups with different consumption habits (e.g. vegetarians) by the application of correction factors. The models are capable of being extended with a view to covering other age groups. (orig.) [de

Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Vutchkov, M.; Lalor, G.C.; Preston, J.

1999-01-01

Air quality has been monitored at selected areas in Jamaica using high volume samplers. The results obtained, showed elevated levels of aluminium in bauxitic areas and very high lead concentrations in urban areas, from 5 to 35 times greater than in rural areas. The lower throughput of the conventional air particulate samplers however, restricts the air quality and health assessment on a nation-wide scale. Biomonitoring offers a cost-effective alternative to air-quality assessment if appropriate indicator species are chosen. The epiphytic lower plants such as lichens and mosses have been used as indicators of regional air quality in several European countries and USA. However, there is not enough studies on lichens and mosses in tropical countries, probably due to the lower occurrence of these species, which cover only 8% of the world's land surface. In Jamaica the epiphytic higher plants, represented by the genus Tillandsia are widely distributed, which make them along with the lichens and mosses potential site-specific bioindicators of air quality. The IAEA Co-ordinated Research Project entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear And Related Analytical Techniques' will address these needs of the country. The primary purpose of the present study was to develop specific bioindicators of atmospheric air pollution in Jamaica, which will provide baseline information for health hazards assessment

Investigation of the quality of stored red blood cells after simulated air drop in the maritime environment.

Science.gov (United States)

Meli, Athinoula; Hancock, Vicky; Doughty, Heidi; Smedley, Steve; Cardigan, Rebecca; Wiltshire, Michael

2018-02-01

Maritime medical capability may be compromised by blood resupply. Air-dropped red blood cells (RBCs) is a possible mitigation factor. This study set out to evaluate RBC storage variables after a simulated parachute air drop into the sea, as limited data exist. The air load construction for the air drop of blood was subject to static drop assessment to simulate a worst-case parachute drop scenario. One control and two test Golden Hour shipping containers were each packaged with 10 RBC units. The control box was not dropped; Test Boxes 1 and 2 were further reinforced with waterproof boxes and underwent a simulated air drop on Day 7 or Day 8 postdonation, respectively. One day after the drop and once a week thereafter until Day 43 of storage, RBCs from each box were sampled and tested for full blood counts, hemolysis, adenosine triphosphate, 2,3-diphosphoglycerate, pH, extracellular potassium, glucose, lactate, deformability, and RBC microvesicles. The packaging configuration completed the air drop with no water ingress or physical damage. All units met UK specifications for volume, hemoglobin, and hemolysis. There were no significant differences for any of the variables studied between RBCs in the control box compared to RBCs in Test Boxes 1 and 2 combined over storage. The test proved that the packaging solution and the impact of a maritime air drop as performed in this study, on Day 7 or Day 8 postdonation, did not affect the in vitro quality of RBCs in SAGM over storage for 35 days. © 2017 AABB.

Measurement of {sup 131}I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment

Energy Technology Data Exchange (ETDEWEB)

Brudecki, K.; Mietelski, J.W. [Polish Academy of Sciences, Institute of Nuclear Physics, Krakow (Poland); Szczodry, A.; Kowalska, A. [Department of Endocrinology and Nuclear Medicine Holycross Cancer Center, Kielce (Poland); Mroz, T. [Pedagogical University in Cracow, Krakow (Poland)

2018-03-15

This paper presents results of {sup 131}I air activity measurements performed within nuclear medical hospitals as a tool for internal dose assessment. The study was conducted at a place of preparation and administration of {sup 131}I (''hot room'') and at a nurse station. {sup 131}I activity measurements were performed for 5 and 4 consecutive working days, at the ''hot room'' and nurse station, respectively. Iodine from the air was collected by a mobile HVS-30 aerosol sampler combined with a gas sampler. Both the gaseous and aerosol fractions were measurement. The activities in the gaseous fraction ranged from (28 ± 1 Bq m{sup -3}) to (492 ± 4) Bq m{sup -3}. At both sampling sites, the activity of the gaseous iodine fraction trapped on activated charcoal was significantly higher than that of the aerosol fraction captured on Petrianov filter cloth. Based on these results, an attempt has been made to estimate annual inhalation effective doses, which were found to range from 0.47 mSv (nurse female) to 1.3 mSv (technician male). The highest annual inhalation equivalent doses have been found for thyroid as 32, 27, 13, and 11 mSv, respectively, for technician male, technical female, nurse male, and nurse female. The method presented here allows to fill the gaps in internal doses measurements. Moreover, because method has been successful used for many years in radioactive contamination monitoring of air in cases of serious nuclear accidents, it should also be used in nuclear medicine. (orig.)

Damage Curves of a Nuclear Reactor Structure exposed to Air Blast Loading

International Nuclear Information System (INIS)

Brandys, I.; Ornai, D.; Ronen, Y.

2014-01-01

Nuclear Power Plant (NPP) radiological hazards due to accidental failure or deliberated attacks are of most concern due to their destructive and global consequences: large area contaminations, injuries, exposure to ionizing radiation (which can cause death or illness, depends on the levels of exposure), loss of lives of both humans and animals, and severe damage to the environment. Prevention of such consequences is of a global importance and it has led to the definition of safety & design guidelines, and regulations by various authorities such as IAEA, U.S. NRC, etc. The guidelines define general requirements for the integrity of a NPP’s physical barriers (such as protective walls) when challenged by external events, for example human induced explosion. A more specific relation to the design of a NPP is that its structures and equipment (reactor building, fuel building, safeguards building, diesel-generator building, pumping station, nuclear auxiliaries building, and effluent treatment building) must function properly: shutdown the reactor, removal of decayed heat, storage of spent fuel, and treatment and containment of radioactive effluents) under external explosion. It requires that the NPP’s structures and equipment resistance to external explosion should be analyzed and verified. The air blast loading created by external explosion, as well as its effects & consequences on different kinds of structures are described in the literature. Structural elements response to the air blast can be analyzed in general by a Single Degree of Freedom (SDOF) system that converts a distributed mass, loads, and resistance to concentrated mass, force, and stiffness located at a representative point of the structure's element where the displacements are the highest one. Proper shielding should be designed if the explosion blast effects are greater than the resistance capacity.External explosion effects should be considered within the Screening Distance Value (SDV) of the NPP

A brief history of the air cleaning conferences

International Nuclear Information System (INIS)

First, M.W.

1995-01-01

I have been asked to prepare a history of the air cleaning conferences. Undertaking such a task is, of course, a wonderful opportunity for reminiscences and a chance to retell old war stories. I must admit that it has taken much longer than I anticipated because I found myself so completely engrossed rereading the old records that time seemed to stop, although the hours passed. But a history of the nuclear air cleaning conferences means more than a stroll down memory lane. The 23 recorded air cleaning conference proceedings reflect an important aspect of the history of major nuclear developments, both military and civilian, because engineered safety features designed to prevent dispersion of radioactive products to the environment have always been a necessity for progress in this field. For this reason, I hope the history of the nuclear air cleaning conferences will not only be enjoyable, but also have meaning for young people entering this field. The air cleaning conferences were an outgrowth of the operations of the U.S. Atomic Energy Commission's (AEC) Stack Gas Working Group established in 1948 to review air cleaning operations at AEC installations. AEC's Division of Engineering sponsored and funded air cleaning research and development at Harvard University's School of Public Health, beginning about the same time. In addition to research and development, the Harvard contract called for consulting and educational services. The latter provided the opportunity for meetings devoted to information on air cleaning that could be applied to ongoing and anticipated nuclear operations

A brief history of the air cleaning conferences

Energy Technology Data Exchange (ETDEWEB)

First, M.W.

1995-02-01

I have been asked to prepare a history of the air cleaning conferences. Undertaking such a task is, of course, a wonderful opportunity for reminiscences and a chance to retell old war stories. I must admit that it has taken much longer than I anticipated because I found myself so completely engrossed rereading the old records that time seemed to stop, although the hours passed. But a history of the nuclear air cleaning conferences means more than a stroll down memory lane. The 23 recorded air cleaning conference proceedings reflect an important aspect of the history of major nuclear developments, both military and civilian, because engineered safety features designed to prevent dispersion of radioactive products to the environment have always been a necessity for progress in this field. For this reason, I hope the history of the nuclear air cleaning conferences will not only be enjoyable, but also have meaning for young people entering this field. The air cleaning conferences were an outgrowth of the operations of the U.S. Atomic Energy Commission`s (AEC) Stack Gas Working Group established in 1948 to review air cleaning operations at AEC installations. AEC`s Division of Engineering sponsored and funded air cleaning research and development at Harvard University`s School of Public Health, beginning about the same time. In addition to research and development, the Harvard contract called for consulting and educational services. The latter provided the opportunity for meetings devoted to information on air cleaning that could be applied to ongoing and anticipated nuclear operations.

OECD MCCI Small-Scale Water Ingression and Crust Strength tests (SSWICS) design report, Rev. 2 October 31, 2002

International Nuclear Information System (INIS)

Farmer, M.; Lomperski, S.; Kilsdonk, D.; Aeschlimann, B.; Pfeiffer, P.

2011-01-01

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are planned to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium (∼φ30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. A description of the test apparatus, instrumentation, data reduction, and test matrix are the subject of the first portion of this report. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The introduction of a thermal gradient across the crust is thought to be important for these tests because of uncertainty in the magnitude of the thermal stresses and thus their relative

Determination and behaviour of plutonium emitted with liquid effluents and exhaust air into the environment of the Nuclear Research Centre Karlsruhe

International Nuclear Information System (INIS)

Schuettelkopf, H.; Pimpl, M.

1986-01-01

The plutonium concentrations in the surroundings of the Karlsruhe Nuclear Research Centre (KfK) are in the range of variation of the global plutonium contamination caused by fallout of atmospheric nuclear tests. Exclusively in the sediments of the Old River Rhine, which serves as main canal for the liquid effluents, higher plutonium concentrations could be detected. The dose exposure of the population living in the environment of the KfK caused by the measured plutonium concentrations is negligible low. From the Karlsruhe Reprocessing Plant (WAK) and the facilities needed to decontaminate radioactive wastes 0.48 GBq (13 mCi) plutonium alpha activity has been emitted within 11 years of operation until 1982 - 1/3 with the liquid effluents and 2/3 with the exhaust air. Following the pathway with the exhaust air, plutonium concentrations in the environment of the Karlsruhe Reprocessing Plant were measured in groundlevel air, in soil, in plants, in food and in animal tissues. Radioecological parameters like dispersion factors, deposition velocities, migration velocities in soil and transfer soil-to-plant were investigated. Following the pathway with the liquid effluents, plutonium concentrations were measured in surface waters, sediments, water plants, plankton and animals. Dilution and sedimentation behaviour were studied as well as the transfer water-to-plant and water-to-animals. (orig.) [de

An overview of the RCA/IAEA activities in the Australasian region using nuclear analysis techniques for monitoring air pollution

International Nuclear Information System (INIS)

Markwitz, Andreas

2005-01-01

The International Atomic Energy Agency (IAEA) via the Regional Co-operative Agreement (RCA) has identified air particulate matter pollution as a major transboundary environmental issue in the Australasian region. Sixteen countries in the region spanning from Pakistan to the Philippines and from China to New Zealand are participating in the regional programme RAS/7/013-Improved information of urban air quality management in the RCA region' that started in 1997. New Zealand is the lead-country for this programme in which nuclear analytical techniques, such as particle induced X-ray emission (PIXE), neutron activation analysis (NAA) and X-ray fluorescence spectrometry (XRF) are used to measure key elements in PM 2.5-0 and PM 10-2.5 filters from GENT stacked samplers collected twice weekly. Major sources of air particulate matter pollution are identified using statistical source apportionment techniques. To identify transboundary air particulate matter pollution events, the data is collated in a large database. Additionally, the data is used by end-users of the participating countries in the programme. An overview is presented. (author)

Reactive inspection response of NRC Region III to potential technical deficiencies identified in recent Nuclear Air Cleaning Conference papers

International Nuclear Information System (INIS)

Gill, C.F.

1987-01-01

In order to effectively meet its responsibility to protect the public health and safety, the Nuclear Regulatory Commission (NRC) nuclear power plant licensing and inspection programs respond to potential technical deficiencies identified by conference and professional society meeting papers when deemed appropriate. The NRC staff's response mechanisms for such technical deficiencies include: generic letters, Bulletins, Information Notices, Standard Review Plan (NUREG-0800) revisions, docketed Final Safety Analysis Report (FSAR) questions, special studies, special (reactive) inspection, and inspection program revisions. This paper describes reactive inspection efforts by Region III in response to potential technical deficiencies identified in recent air cleaning conference papers, including: post-accident effluent sample line deposition losses; failure to implement good engineering practices in the design, construction, and testing of Nuclear Air Treatment Systems (NATS); filter bypass via filter housing drain lines; spinster carbon degradation; use of silicone sealants and other temporary patching material in NATS; filter housing fire protection deluge system problems; lack of charcoal batch traceability; Quality Assurance records problems involving equipment, vendor, filter, and personnel qualifications; inadequate ANSI/ASME N510 acceptance criteria and tests; and failure to adequately demonstrate control room habitability per 10 CFR 50, Appendix A, General Design Criterion-19. Region III inspections indicate that many of these deficiencies appear to be prevalent. Inspection findings and utility responses to the findings are discussed. NRC Region III and Headquarters programmatic reactions to the identified generic problem areas are also discussed

Application of CPML to two-dimension numerical simulation of nuclear electromagnetic pulse from air explosions

International Nuclear Information System (INIS)

Gao Chunxia; Wang Lianghou

2005-01-01

The characteristics of different types of PML were analyzed and the convolutional PML was chosen to truncate the open boundaries in numerical simulation of nuclear electromagnetic pulse from air explosions. On the basis of the split-field PML and the plane-wave solution of electromagnetic field in free space, the unsplit-field PML was constructed. By applying the convolutional theorem of Fourier transform, the discrete iterative equations of electromagnetic field components were presented in the CPML media under the two-dimension prolate-spheroidal coordinate system. The numerical results indicate that the method of CPML can largely decrease calculation errors of boundary fields. (authors)

Order of 31 July 1987 on protection and control of nuclear materials carried by air

International Nuclear Information System (INIS)

1987-01-01

This Order is part of a series of texts on protection and control of nuclear materials which include: the Act of 25 July 1980 and the Decree of 12 May 1981 made in its implementation and, as regards the specific aspect of protection and control of materials during transport, the Order of 26 March 1982 amended in 1986. The 1987 Order lays down the conditions which must be complied with by approved carriers (the French or the foreign holders of a licence under the above-mentioned Act of 1980) in case of transport of such materials by air [fr

Spent nuclear fuel storage device and spent nuclear fuel storage method using the device

International Nuclear Information System (INIS)

Tani, Yutaro

1998-01-01

Storage cells attachably/detachably support nuclear fuel containing vessels while keeping the vertical posture of them. A ventilation pipe which forms air channels for ventilating air to the outer circumference of the nuclear fuel containing vessel is disposed at the outer circumference of the nuclear fuel containing vessel contained in the storage cell. A shielding port for keeping the support openings gas tightly is moved, and a communication port thereof can be aligned with the upper portion of the support opening. The lower end of the transporting and containing vessel is placed on the shielding port, and an opening/closing shutter is opened. The gas tightness is kept by the shielding port, the nuclear fuel containing vessel filled with spent nuclear fuels is inserted to the support opening and supported. Then, the support opening is closed by a sealing lid. (I.N.)

Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

Energy Technology Data Exchange (ETDEWEB)

Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

1997-10-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

POTENTIAL FOR HYDROGEN BUILDUP IN HANFORD SEALED AIR FILLED NUCLEAR STORAGE VESSELS

International Nuclear Information System (INIS)

HEY BE

2008-01-01

This calculation is performed in accordance with HNF-PRO-8259, PHMC Calculation Preparation and Issue and addresses the question as to whether a flammable mixture of hydrogen gas can accumulate in a Hanford sealed nuclear storage vessel where the only source of hydrogen is the moisture in the air that initially filled the vessel Of specific concern is nuclear fuel inside IDENT 69-Gs, placed in Core Component Containers (CCCs) located inside Interim Storage Vaults (ISVs) at the Plutonium Finishing Plant (PFP) The CCCs are to be removed from the ISVs and placed inside a Hanford Unirradiated Fuel Package (HUFP) for transport and interim storage. The repackaging procedures mandated that no plastics were permitted, all labels and tape were to be removed and the pins to be clean and inspected Loading of the fuel into the CCC/ISV package was permitted only if it was not raining or snowing. This was to preclude the introduction of any water The purpose was to minimize the presence of any hydrogenous material inside the storage vessels. The scope of NFPA 69, 'Standard on Explosion Prevention Systems', precludes its applicability for this case. The reactor fuel pins are helium bonded. The non-fuel pins, such as the pellet stacks, are also helium bonded. The fuel pellets were sintered at temperatures that preclude any residual hydrogenous material. Hydrogen gas can be formed from neutron and gamma radiolysis of water vapor. The radiolysis reaction is quite complex involving several intermediate radicals, and competing recombination reactions. Hydrogen gas can also be formed through corrosion. This analysis takes a simplistic approach and assumes that all water vapor present in the storage vessel is decomposed into hydrogen gas. Although the analysis is needed to specifically address HUFP storage of nuclear fuel, it is equally applicable to any sealed fuel storage vessel under the assumptions listed

Safety-related control air systems

International Nuclear Information System (INIS)

Anon.

1977-01-01

This Standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This Standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this Standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

Protective action evaluation, Part 1. Effectiveness of sheltering as a protective action against nuclear accidents involving gaseous releases

International Nuclear Information System (INIS)

Anno, G.H.; Dore, M.A.

1978-04-01

In an airborne release of radioactive material from a nuclear power plant accident, sheltering of individuals is of importance in emergency protective action planning. An analysis to estimate the effectiveness or benefit that might be derived from sheltering is described. The objective of this effort is the development of sheltering effectiveness information for those responsible for formulating required emergency plans for nuclear power plant siting. Shelter effectiveness is specifically defined as the dose reduction factor (DRF). DRF estimates for different conditions of source release, shelter structure assumptions, and operational time parameters are made for both whole-body and thyroid doses separately, based on a single-compartment structural model of the time-varying outside and inside gaseous radionuclide sources of krypton, zenon, and iodine. Design basis accident (DBA) assumptions are made for the gaseous radionuclide release. The magnitude of the release and dose estimates are based on radionuclide data from The Reactor Safety Study (WASH-1400). Source release time and duration assumptions are related to release categories PWR 1, PWR 3, and PWR 4, for which release times range from 1.5 to 2.5 hr and the release duration ranges from 0.5 to 3 hr. The basic shelter model characteristics considered are gamma ray attentuation, source geometry, gaseous fission-product ingress, and air change rate. Temporal parameters considered are source release time and duration, cloud travel time, and time spent in the shelter structure. Also, the analysis of shelter effectiveness is based on a time-frame model, which can be conveniently related to other operational times important for emergency planning. In addition to developing shelter-effectiveness estimates parametrically, the advantage of exiting and evacuating the vicinity of the shelter area after some initial time in the shelter is analyzed from the standpoint of the DRF and temporal considerations

78 FR 58970 - Airworthiness Directives; The Boeing Company Airplanes

Science.gov (United States)

2013-09-25

... caused by moisture or condensation being collected inside the display units during operation in hot and... moisture or condensation ingress. The most frequent instance was display units being cold soaked by the air...

Nuclear law in progress

International Nuclear Information System (INIS)

Manóvil, Rafael Mariano

2014-01-01

The 21. AIDN / INLA Congress was organized by the International Nuclear Law Association, in Buenos Aires, between the October 20 and 23, 2014. In this event, were presented almost 50 papers about these subjects: radioactive sources, safety and licensing, radioactive waste management, radiation protection, nuclear transport, security and non-proliferation, nuclear liability and insurance, etc.

Retention of fission products in air filters

International Nuclear Information System (INIS)

Sobnack, R.

1986-01-01

The plume from the Chernobyl nuclear reactor reached London in the morning of 1st May. Less than two weeks later, the Physics Department, University of Surrey, reported a measurable level of radioactivity in air filters. On 15th May air filters from within the air conditioning plant of the Radioisotope Department at the London Hospital were removed for radiation checks. Crude tests with a geiger counter gave readings of 5-10 times higher than background levels. Gamma-ray spectroscopy of the departmental air filters (AF1) using a 127 mm NaI detector revealed a pattern characteristic of emissions of fission products from a nuclear reactor. Another air filter (AF2), from the home of a member of staff, was much less active. Because of the complexity of the gamma-ray spectrum and the relatively high level of emission from the departmental air filter, a thorough investigation was carried out using a high purity germanium detector. (author)

Subway platform air quality: Assessing the influences of tunnel ventilation, train piston effect and station design

Science.gov (United States)

Moreno, T.; Pérez, N.; Reche, C.; Martins, V.; de Miguel, E.; Capdevila, M.; Centelles, S.; Minguillón, M. C.; Amato, F.; Alastuey, A.; Querol, X.; Gibbons, W.

2014-08-01

A high resolution air quality monitoring campaign (PM, CO2 and CO) was conducted on differently designed station platforms in the Barcelona subway system under: (a) normal forced tunnel ventilation, and (b) with daytime tunnel ventilation systems shut down. PM concentrations are highly variable (6-128 μgPM1 m-3, 16-314 μgPM3 m-3, and 33-332 μgPM10 m-3, 15-min averages) depending on ventilation conditions and station design. Narrow platforms served by single-track tunnels are heavily dependent on forced tunnel ventilation and cannot rely on the train piston effect alone to reduce platform PM concentrations. In contrast PM levels in stations with spacious double-track tunnels are not greatly affected when tunnel ventilation is switched off, offering the possibility of significant energy savings without damaging air quality. Sampling at different positions along the platform reveals considerable lateral variation, with the greatest accumulation of particulates occurring at one end of the platform. Passenger accesses can dilute PM concentrations by introducing cleaner outside air, although lateral down-platform accesses are less effective than those positioned at the train entry point. CO concentrations on the platform are very low (≤1 ppm) and probably controlled by ingress of traffic-contaminated street-level air. CO2 averages range from 371 to 569 ppm, changing during the build-up and exchange of passengers with each passing train.

Ignition properties of nuclear grade activated carbons

International Nuclear Information System (INIS)

Freeman, W.P.; Hunt, J.R.; Kovach, J.L.

1983-01-01

The ignition property of new activated carbons used in air cleaning systems of nuclear facilities has been evaluated in the past, however very little information has been generated on the behavior of aged, weathered carbons which have been exposed to normal nuclear facility environment. Additionally the standard procedure for evaluation of ignition temperature of carbon is performed under very different conditions than those used in the design of nuclear air cleaning systems. Data were generated evaluating the ageing of activated carbons and comparing their CH 3 131 I removal histories to their ignition temperatures. A series of tests were performed on samples from one nuclear power reactor versus use time, a second series evaluated samples from several plants showing the variability of atmospheric effects. The ignition temperatures were evaluated simulating the conditions existing in nuclear air cleaning systems, such as velocity, bed depth, etc., to eliminate potential confusion resulting from artifically set current standard conditions

Respirator studies for the Nuclear Regulatory Commission. Protection factors for supplied-air respirators. Progress report, October 1, 1976--September 30, 1977

International Nuclear Information System (INIS)

Hack, A.; Bradley, O.D.; Trujillo, A.

1977-12-01

This report describes the work performed during FY 1977 for the Nuclear Regulatory Commission. The Protection Factors (efficiency) provided by 25 NIOSH approved supplied-air respirators were determined while the devices were worn by a panel of anthropometrically selected test subjects. The major recommendation was that demand-type respirators should neither be used nor approved

Evolution of the groundwater chemistry around a nuclear waste repository

International Nuclear Information System (INIS)

Haworth, A.; Sharland, S.M.; Tasker, P.W.; Tweed, C.J.

1987-12-01

Some of the necessary techniques to construct a research model of the evolution of the groundwater under the influence of the backfill material in a nuclear waste repository are developed. These involve various extensions to the coupled ionic migration and chemical equilibria code, CHEQMATE. These extensions have been used in the first stages of a model of the chemical environment within the host rock. In this preliminary model we have considered a concrete backfill material embedded in a clay geology. However, the model is sufficiently flexible that other backfill materials and host rocks may be considered if a good thermodynamical description is available. The preliminary results from the model suggest that over timescales of about a thousand years the natural buffering action of the clay against changes in pH has a significant effect on the scale of perturbation by the ingress of highly alkaline porewater. It seems likely therefore that this type of modelling will have considerable relevance to the safety assessment models. (author)

Ninth Argentine congress on biology and nuclear medicine; fourth Southernmost sessions of ALASBIMN (Latin-American Association of Biology and Nuclear Medicine); first Spanish-Argentine congress on nuclear medicine; first Argentine sessions on nuclear cardiology

International Nuclear Information System (INIS)

1991-01-01

This work deals with all the papers presented at the 9. Argentine congress on biology and nuclear medicine; IV Southernmost sessions of ALASBIMN; I Spanish-Argentine congress on nuclear medicine and I Sessions Argentine sessions on nuclear cardiology held in Buenos Aires, Argentina, from October 14 - 18, 1991

Water Resistant Container Technical Basis Document for the TA-55 Criticality Safety Program

Energy Technology Data Exchange (ETDEWEB)

Smith, Paul Herrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Teague, Jonathan Gayle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-04-30

Criticality safety at TA-55 relies on nuclear material containers that are water resistant to prevent significant amounts of water from coming into contact with fissile material in the event of a fire that causes a breach of glovevbox confinement and subsequent fire water ingress. A “water tight container” is a container that will not allow more than 50ml of water ingress when fully submerged, except when under sufficient pressure to produce structural discontinuity. There are many types of containers, welded containers, hermetically sealed containers, filtered containers, etc.

Nuclear winter or nuclear fall?

Science.gov (United States)

Berger, André

Climate is universal. If a major modern nuclear war (i.e., with a large number of small-yield weapons) were to happen, it is not even necessary to have a specific part of the world directly involved for there to be cause to worry about the consequences for its inhabitants and their future. Indeed, smoke from fires ignited by the nuclear explosions would be transported by winds all over the world, causing dark and cold. According to the first study, by Turco et al. [1983], air surface temperature over continental areas of the northern mid-latitudes (assumed to be the nuclear war theatre) would fall to winter levels even in summer (hence the term “nuclear winter”) and induce drastic climatic conditions for several months at least. The devastating effects of a nuclear war would thus last much longer than was assumed initially. Discussing to what extent these estimations of long-term impacts on climate are reliable is the purpose of this article.

Oxidation and Volatilization from Tantalum Alloy T-222 During Air Exposure

Energy Technology Data Exchange (ETDEWEB)

Smolik, Galen Richard; Petti, David Andrew; Sharpe, John Phillip; Schuetz, Stanley Thomas

2000-10-01

Tantalum alloys are one of the refractory metals with renewed consideration for high temperatures in fusion reactor applications. Tantalum alloys perform well in protective environments but oxidized readily in gases containing higher oxygen levels. In addition, the radioactive isotope Ta-182 would be produced in tantalum and could be a significant contributor to dose if mobilized. Other isotopes of importance are produced from tungsten and hafnium. Mobilization of activated products during an accident with air ingress is therefore a safety issue. In this study, we measured the extent of oxidation and mobilization from tantalum alloy T-222 oxidized in flowing air between 500 and 1200°C. This alloy nominally contains 10 wt% tungsten, 2.5 wt% hafnium and 0.01 wt% carbon. We found that the mobilization of Ta and Hf was closely linked to the occurrence of oxide spalling. These elements showed no migration from the test chamber. Some W was mobilized by volatilization as evidenced by transport from the chamber. Tungsten volatilization could occur primarily during initial stages of oxidation before an oxide scale forms and impedes the process. The mobilization of Ta and W are presented in terms of the mass flux (g/m 2 -h) as a function of test temperature. These measurements along with specific designs, activation calculations, and accident scenarios provide information useful for dose calculations of future fusion devices

Oxidation and Volatilization from Tantalum Alloy T-222 During Air Exposure

Energy Technology Data Exchange (ETDEWEB)

Smolik, G.R.; Petti, D.A.; Sharpe, J.P.; Schuetz, S.T.

2000-10-31

Tantalum alloys are one of the refractory metals with renewed consideration for high temperatures in fusion reactor applications. Tantalum alloys perform well in protective environments but oxidized readily in gases containing higher oxygen levels. In addition, the radioactive isotope Ta-182 would be produced in tantalum and could be a significant contributor to dose if mobilized. Other isotopes of importance are produced from tungsten and hafnium. Mobilization of activated products during an accident with air ingress is therefore a safety issue. In this study, we measured the extent of oxidation and mobilization from tantalum alloy T-222 oxidized in flowing air between 500 and 1200 C. This alloy nominally contains 10 wt% tungsten, 2.5 wt% hafnium and 0.01 wt% carbon. We found that the mobilization of Ta and Hf was closely linked to the occurrence of oxide spalling. These elements showed no migration from the test chamber. Some W was mobilized by volatilization as evidenced by transport from the chamber. Tungsten volatilization could occur primarily during initial stages of oxidation before an oxide scale forms and impedes the process. The mobilization of Ta and W are presented in terms of the mass flux (g/m 2 -h) as a function of test temperature. These measurements along with specific designs, activation calculations, and accident scenarios provide information useful for dose calculations of future fusion devices.

Air temperature determination inside residual heat removal pump room of Angra-1 nuclear power plant after a design basic accident

International Nuclear Information System (INIS)

Siniscalchi, Marcio Rezende

2005-01-01

This work develops heat transfer theoretical models for determination of air temperature inside the Residual Heat Removal Pump Room of Angra 1 Nuclear Power Plant after a Design Basis Accident without forced ventilation. Two models had been developed. The differential equations are solved by analytical methods. A software in FORTRAN language are developed for simulations of temperature inside rooms for different geometries and materials. (author)

Layup practices at EDF PWR fleet and future developments

International Nuclear Information System (INIS)

Ramos, Olga Alos; Pablo, Sergio De Maria; Wintergerst, Matthieu

2014-01-01

A proper lay-up can only be achieved by plant specific lay-up procedures. The layup control practices are necessary to prevent corrosion damage during shutdown and are an important part of the life time extension of a nuclear power plant. EDF operational experience in this area confirms that damage to plant equipment from improper layup procedures is a cause of reduced plant reliability and availability and can increase the corrosion products ingress into the SG during start-up. The plant preservation strategy applied across the EDF fleet is based on the following principles: Anticipated time frame of the required layup: short-term outages can become long-term outages, and can necessitate the use of unplanned preservation techniques. Dry layup for a long-term outage of the condensate/feedwater system: condenser vacuum assisted draining at high temperature, estimation of air requirements (flow rate, humidity...) to guarantee the optimum conditions inside the system. Wet lay up for a short-term outage of the condensate/feedwater system: system filled with operating medium, avoiding air ingress into the system, injection of chemical agents if necessary. Dry lay-up or wet lay up for the steam generators depending on maintenance work or radiation protection needed. This article presents the EDF layup program and the improvements in layup practices. It provides information on the layup procedures, best practices and recommendations, operating experience, considerations for different durations of outages; the implementation of a preservation working group, the selection of the systems that will be included in the lay-up program. Finally, future developments will be presented, such as the development of a 'convective model' to determine air requirements (humidity, flow rate...) and the drying rate to dry a heat exchanger. (author)

Development of Very High Temperature Reactor Technology

International Nuclear Information System (INIS)

Lee, Won Jae; Noh, J. M.; Kim, Y. H.

2009-04-01

For an efficient production of nuclear hydrogen, the VHTR (Very High Temperature Gas-cooled Reactor) of 950 .deg. C outlet temperature and the interfacing system for the hydrogen production are required. We have developed various evaluation technologies for the performance and safety of VHTR through the accomplishment of this project. First, to evaluate the performance of VHTR, a series of analyses has been performed such as core characteristics at 950 .deg. C, applicability of cooled-vessel, intermediate loop system and high temperature structural integrity. Through the analyses of major accidents such as HPCC and LPCC and the analysis of the risk/performance-informed method, VHTR safety evaluation has been also performed. In addition, various design analysis codes have been developed for a nuclear design, system loop design, system performance analysis, air-ingress accident analysis, fission product/tritium transport analysis, graphite structure seismic analysis and hydrogen explosion analysis, and they are being verified and validated through a lot of international collaborations

A risk-based review of Instrument Air systems at nuclear power plants

International Nuclear Information System (INIS)

DeMoss, G.; Lofgren, E.; Rothleder, B.; Villeran, M.; Ruger, C.

1990-01-01

The broad objective of this analysis was to provide risk-based information to help focus regulatory actions related to Instrument Air (IA) systems at operating nuclear power plants. We first created an extensive data base of summarized and characterized IA-related events that gave a qualitative indication of the nature and severity of these events. Additionally, this data base was used to calculate the frequencies of certain events, which were used in the risk analysis. The risk analysis consisted of reviewing published PRAs and NRC Accident Sequence Precursor reports for IA-initiated accident sequences, IA interactions with frontline systems, and IA-related risk significant events. Sensitivity calculations were performed when possible. Generically, IA was found to contribute less to total risk than many safety systems; however, specific design weaknesses in safety systems, non-safety systems, and the IA system were found to be significant in risk. 22 refs., 13 figs., 24 tabs

Heating, ventilating, and air-conditioning applications

International Nuclear Information System (INIS)

Anon.

1991-01-01

This book covers: Comfort air conditioning and heating of residences: Space HVAC systems; Industrial and special air conditioning and ventilation for nuclear facilities, and for mines; Energy sources, such as Geothermal energy, solar utilization, and energy resources; Building operation and maintenance; energy management, and Thermal storage

Index to the 1st through 16th AEC/ERDA/DOE nuclear air cleaning conferences

International Nuclear Information System (INIS)

Burchsted, C.A.

1981-02-01

The Proceedings of the sixteen conferences comprise a vertible encyclopedia on the technology of nuclear air and gas treatment and the control of airborne nuclear waste. These Proceedings cover the history of the technology; describe most of the research and developments in the field, worldwide, since the early 1950's; describe the problems that have been encountered and the solutions found to those problems; and summarize experience with equipment and systems developed for the control of airborne radioactive wastes in laboratory, radiochemical, and reactor operations, both government and commercial. The problem with this encyclopedia is that there has been no index to it; there has been no easy way for searching it to find what was available. This index fills the gap. The first conference was an informal meeting of a number of interested parties from among the then AEC contractors. Consequently, there were no proceedings for that meeting. The subsequent conferences, with their years, locations, and Proceedings numbers, are listed. This index consists of three parts: a tabulation of papers and their authors by paper number (Part I); a tabulation of papers and their paper numbers by author (Part II); and a key-word-in context (KWIC) index of papers. The paper number is a two-part designation consisting of the number of the conference (2, 3...16) followed by the page number of the paper in the corresponding Proceedings. The author index lists each author who has participated in the air cleaning conferences over the years, and the paper index lists all authors of the respective papers. The KWIC index is, in effect, a comprehensive subject cross index; each paper is listed as many times, by keyword, as there are major terms (i.e., keywords) in its title. Although this multiple listing results in a lengthy list, it provides a very deep cross-indexing of the papers

Cooperative activation of transcription by autoimmune regulator AIRE and CBP

International Nuclear Information System (INIS)

Pitkaenen, J.; Rebane, A.; Rowell, J.; Murumaegi, A.; Stroebel, P.; Moell, K.; Saare, M.; Heikkilae, J.; Doucas, V.; Marx, A.; Peterson, P.

2005-01-01

Autoimmune regulator (AIRE) is a transcriptional regulator that is believed to control the expression of tissue-specific genes in the thymus. Mutated AIRE is responsible for onset of the hereditary autoimmune disease APECED. AIRE is able to form nuclear bodies (NBs) and interacts with the ubiquitous transcriptional coactivator CBP. In this paper, we show that CBP and AIRE synergistically activate transcription on different promoter reporters whereas AIRE gene mutation R257X, found in APECED patients, interferes with this coactivation effect. Furthermore, the overexpression of AIRE and CBP collaboratively enhance endogenous IFNβ mRNA expression. The immunohistochemical studies suggest that CBP, depending on the balance of nuclear proteins, is a component of AIRE NBs. We also show that AIRE NBs are devoid of active chromatin and, therefore, not sites of transcription. In addition, we demonstrate by 3D analyses that AIRE and CBP, when colocalizing, are located spatially differently within AIRE NBs. In conclusion, our data suggest that AIRE activates transcription of the target genes, i.e., autoantigens in collaboration with CBP and that this activation occurs outside of AIRE NBs

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

Energy Technology Data Exchange (ETDEWEB)

Aldape U, F [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-10-15

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

Initial substantial reduction in air dose rates of Cs origin and personal doses for residents owing to the Fukushima nuclear accident

International Nuclear Information System (INIS)

Yoshida, Hiroko; Saito, Junko; Hirasawa, Noriyasu; Kobayashi, Ikuo

2013-01-01

The initial substantial reduction in the air dose rate and personal dose equivalent [Hp(10)] for residents were compared between the Marumori and Kosugo regions for the period from September 2011 to September 2012 after the occurrence of the Fukushima nuclear accident. Marumori is a rural settlement, and Kosugo is a suburban city along a freeway. A similar tendency was observed in the Hp(10) results for Marumori residents and in the air dose rates for both regions: values dropped during the heavy snow season and a faster reduction in the air dose rate than the radioactive decay of 134 Cs and 137 Cs was observed after the snow had thawed. These reductions are considered to be caused by the weathering and/or migration of radionuclides down the soil column. However, neither a drop due to an accumulation of snow nor faster reduction was observed in Hp(10) for Kosugo residents. This discrepancy between the air dose rate and Hp(10) for Marumori and Kosugo residents might be caused by differences in their living environment. (author)

Air leakage analysis of research reactor HANARO building in typhoon condition for the nuclear emergency preparedness

Energy Technology Data Exchange (ETDEWEB)

Lee, Goany Up; Lee, Hae Cho; Kim, Bong Seok; Kim, Jong Soo; Choi, Pyung Kyu [Dept. of Emergency Preparedness, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. It was found that the leak rate is 0.1%·day{sup -1} of air, 0.004%·day{sup -1} of noble gas and 3.7×10{sup -5}%·day{sup -1} of aerosol during typhoon passing. The air leak rate of 0.1%·day can be converted into 1.36 m{sup 3}·hr{sup -1} , but the design leak rate in HANARO safety analysis report was considered as 600 m3·hr{sup -1} under the condition of 20 m·sec{sup -1} wind speed outside of the building by typhoon. Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor.

Air leakage analysis of research reactor HANARO building in typhoon condition for the nuclear emergency preparedness

International Nuclear Information System (INIS)

Lee, Goany Up; Lee, Hae Cho; Kim, Bong Seok; Kim, Jong Soo; Choi, Pyung Kyu

2016-01-01

To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. It was found that the leak rate is 0.1%·day -1 of air, 0.004%·day -1 of noble gas and 3.7×10 -5 %·day -1 of aerosol during typhoon passing. The air leak rate of 0.1%·day can be converted into 1.36 m 3 ·hr -1 , but the design leak rate in HANARO safety analysis report was considered as 600 m3·hr -1 under the condition of 20 m·sec -1 wind speed outside of the building by typhoon. Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor

Instrument air system - Aging impact on system availability

International Nuclear Information System (INIS)

Villaran, M.; Subudhi, M.

1989-01-01

As part of ongoing efforts to understand and manage the effects of aging in nuclear power plants, an aging assessment was performed for the Instrument Air (IA) system, a system that has been the subject of much scrutiny in recent years. Despite its non-safety classification, instrument air has been a factor in a number of potentially serious events. This report presents the results of the assessment and discusses the impact of instrument air system aging on system availability and plant safety. This work was performed for the US Nuclear Regulatory Commission (NRC) as part of the Nuclear Plant Aging Research (NPAR) program. To perform the complex task of analyzing an entire system, the Aging and Life Extension Assessment Program (ALEAP) System Level Plan was developed by Brookhaven National Laboratory and applied successfully in previous system aging studies. The work presented herein was performed using two parallel work paths, as described in the ALEAP plant. One path used deterministic techniques to assess the impact of aging on compressed air system performance, while the second path used probabilistic methods. Results from both paths then were used to characterize aging in the instrument air system. Some conclusions from this work are: compressors, air system valves, and air dryers were found to make up the majority of failures; the effectiveness and quantity of preventive maintenance devoted to a component significantly affected the amount of failures experienced; review of compressed air system designs and studies using a PRA-based system model revealed that the redundancy of key components (compressors, dryers, IA/SA crossconnect valve) was an important factor in system availability; total loss of air events are uncommon

Breathing easier: Indonesia works towards cleaner air

International Nuclear Information System (INIS)

Madsen, Michael Amdi

2015-01-01

Indonesians can look forward to breathing cleaner air following upcoming changes in regulations introduced as a result of a study conducted using nuclear analytical techniques. Lead pollution and other fine particulate matter in the air is now, for the first time, being accurately monitored and is giving Indonesian officials a good understanding of their air pollution problem and how to manage it.

Act no 388 to amend Section 15 of the Nuclear Liability Act

International Nuclear Information System (INIS)

1986-01-01

Finland is ratifying the Montreal Protocols Nos 3 and 4 to the Warsaw Convention concerning carriage by air; protocol No 4 contains no exclusion clause for nuclear damage. This Act amends the 1972 Nuclear Liability Act to the effect that air carriers of nuclear substances have a right of recourse against the operator liable under nuclear legislation. In this way the principle of channelling liability onto the nuclear operator is maintained. (NEA) [fr

Simulation of the air flows in many industrial pleated filters

International Nuclear Information System (INIS)

Del Fabbro, L.; Brun, P.; Laborde, J.C.; Lacan, J.; Ricciardi, L.; Renoux, A.

2000-01-01

The study presents results concerning the characterization of the charge loss and the air flow in nuclear and automobile type pleated filters. The experimental studies in correlation with the numerical models showed an homogenous distribution of the air flows in a THE nuclear type filter, whereas the distribution is heterogenous in the case of an automobile filter. (A.L.B.)

Nuclear physics workshop

International Nuclear Information System (INIS)

1988-01-01

This Workshop in Nuclear Physics related to the TANDAR, took place in Buenos Aires in April from 23 to 26, 1987, with attendance of foreign scientists. There were presented four seminars and a lot of studies which deal with the following fields: Nuclear Physics at medium energies, Nuclear Structure, Nuclear Reactions, Nuclear Matter, Instrumentation and Methodology for Nuclear Spectroscopy, Classical Physics, Quantum Mechanics and Field Theory. It must be emphasized that the Electrostatic Accelerator TANDAR allows to work with heavy ions of high energy, that opens a new field of work in PIXE (particle induced X-ray emission). This powerful analytic technique makes it possiblethe analysis of nearly all the elements of the periodic table with the same accuracy. (M.E.L.) [es

Atmospheric Tracer Depletion Testing for Unfiltered Air In-Leakage Determination at the Wolf Creek Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Sullivan, T. M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wilke, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Roberts, T. [Brookhaven National Lab. (BNL), Upton, NY (United States); Vignato, G. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-03-01

Atmospheric Tracer Depletion tests were conducted at the Wolf Creek Nuclear Power Plant to quantify the unfiltered in-leakage (UI) into the Control Room (CR), Control Building (CB), and Equipment Rooms (ER) at the Wolf Creek Nuclear Power Plant. Wolf Creek has two independent charcoal filter Emergency Ventilation Systems (EVS) that can be used to purify air entering the control building and control room. The Bravo System contains a filtration system in Room 1501 in the Auxiliary Building for the Control Room and another filtration system (FGK02B) on Elevation 2016 for the Control Building. The Alpha system contains a filtration system in Room 1512 in the Auxiliary Building for the Control Room and another filtration system (FGK02A) on Elevation 2016 for the Control Building. The Atmospheric Tracer Depletion (ATD) test is a technique to measure in-leakage using the concentration of perfluorocarbon compounds that have a constant atmospheric background. These levels are present in the Control Room and Control Building under normal operating conditions. When air is supplied by either of the EVS, most of the PFTS are removed by the charcoal filters. If the concentrations of the PFTs measured in protected areas are the same as the levels at the output of the EVS, the in-leakage of outside air into the protected area would be zero. If the concentration is higher in the protected area than at the output of the filter system, there is in-leakage and the in-leakage can be quantified by the difference. Sampling was performed using state-of-the-art Brookhaven Atmospheric Tracer Samplers (BATS) air sampling equipment and analysis performed on Brookhaven National Laboratory (BNL) dedicated PFT analytical systems. In the Alpha test two tracers PMCH and mcPDCH were used to determine in-leakage into the control building. The analytical system was tuned to maximize sensitivity after initial analysis of the Alpha test. The increased sensitivity permitted accurate quantification of

Atmospheric Tracer Depletion Testing for Unfiltered Air In-Leakage Determination at the Wolf Creek Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Sullivan, T. M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wilke, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Roberts, T. [Brookhaven National Lab. (BNL), Upton, NY (United States); Vignato, G. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-04-01

Atmospheric Tracer Depletion tests were conducted at the Wolf Creek Nuclear Power Plant to quantify the unfiltered in-leakage (UI) into the Control Room (CR), Control Building (CB), and Equipment Rooms (ER) at the Wolf Creek Nuclear Power Plant. Wolf Creek has two independent charcoal filter Emergency Ventilation Systems (EVS) that can be used to purify air entering the control building and control room. The Bravo System contains a filtration system in Room 1501 in the Auxiliary Building for the Control Room and another filtration system (FGK02B) on Elevation 2016 for the Control Building. The Alpha system contains a filtration system in Room 1512 in the Auxiliary Building for the Control Room and another filtration system (FGK02A) on Elevation 2016 for the Control Building.The Atmospheric Tracer Depletion (ATD) test is a technique to measure in-leakage using the concentration of perfluorocarbon compounds that have a constant atmospheric background. These levels are present in the Control Room and Control Building under normal operating conditions. When air is supplied by either of the EVS, most of the PFTS are removed by the charcoal filters. If the concentrations of the PFTs measured in protected areas are the same as the levels at the output of the EVS, the in-leakage of outside air into the protected area would be zero. If the concentration is higher in the protected area than at the output of the filter system, there is in-leakage and the in-leakage can be quantified by the difference.Sampling was performed using state-of-the-art Brookhaven Atmospheric Tracer Samplers (BATS) air sampling equipment and analysis performed on Brookhaven National Laboratory (BNL) dedicated PFT analytical systems. In the Alpha test two tracers PMCH and mcPDCH were used to determine in-leakage into the control building. The analytical system was tuned to maximize sensitivity after initial analysis of the Alpha test. The increased sensitivity permitted accurate quantification of five

Probabilistic reconstruction of internal exposure for nuclear power plant workers using air concentration measurements

International Nuclear Information System (INIS)

Linkov, I.; Burmistrov, D.

2000-01-01

Air surveys, whole-body counting, bioassays or combination of these measurements can be utilized for purposes or assessing internal doses to determine compliance with occupational dose equivalent limits. Air sampling with a little support provided by whole body counting and/or bioassays was often relied on in dose calculations. The utility of air sampling for internal dose reconstruction is addressed in this paper through the probabilistic analysis of environmental factors and their impact on dose estimates. In this paper we attempt to reconstruct an internal dose due to inhalation of beta + gamma emitting radionuclides for a contractual electrician, Mr. X. The data available for reconstruction of internal dose for Mr. X was found to be highly variable and uncertain. Uncertainty describes a lack of knowledge about a parameter, this lack of knowledge theoretically can be reduced, e.g., if more measurements were to be taken (for example, estimated activities for alpha-emitting radionuclides are uncertain due to the influence of naturally-occurring alpha-emitters). Variability describes the existence of different values that represent different environmental conditions (for example, the air concentrations of radionuclides may vary over time because of the different tasks performed by workers in the area). Variability can not be reduced by additional data collection because the varying values reflect the variable nature of the environment, not a lack of data. The high variability in measured air concentrations in the restricted areas of a LWR nuclear power plant where he worked do not allow adequate reconstruction of his individual internal dose using deterministic methods and therefore probabilistic methods are desirable. The guidance for probabilistic assessment developed by the United States Environmental Protection Agency as well as recommendations of the National Council of Radiation Protection provide an adequate framework for probabilistic reconstruction of

Air pollution in Thailand using nuclear-related analytical techniques

International Nuclear Information System (INIS)

Leelhaphunt, N.; Chueinta, W.

1994-01-01

The methods of neutron activation, both instrumental and radiochemical, and atomic absorption spectrophotometry are used in a study of the concentrations of Al, As, Br, Cd, Cl, Co, Cr, Cu, Fe, Hg, Mn, Sb, Sc, Se, Si, V, Zn and Pb in airborne particulate matter collected from 7 permanent and 9 temporary air quality monitoring stations. The location of the stations are urban residential, suburban residential, mixed (commercial and residential), commercial and industrial areas and near major roads in Bangkok Metropolitan areas. Air sampling is performed once a month for 24 hours continuously using the high volume air sampler (GMW 2000 H) and for 5, 10, and 15 days continuously using an Anderson Air Sampler (SIBATA AN-200). The elements As, Cd and Cu are determined destructively using ion exchange chromatography while Hg and Se are determined by the dry combustion technique. The determination of Pb was done by atomic absorption spectrophotometry. The results of Pb concentrations in airborne particulate matters, collected during 1987 to 1991, were reported by the Office of the National Environment Board. Levels of Pb content were found to be lower than the National Ambient Air Quality Standards. (author). 3 refs, 4 tabs

Air pollution meteorology

Energy Technology Data Exchange (ETDEWEB)

Shirvaikar, V V; Daoo, V J [Environmental Assessment Div., Bhabha Atomic Research Centre, Mumbai (India)

2002-06-01

This report is intended as a training cum reference document for scientists posted at the Environmental Laboratories at the Nuclear Power Station Sites and other sites of the Department of Atomic Energy with installations emitting air pollutants, radioactive or otherwise. Since a manual already exists for the computation of doses from radioactive air pollutants, a general approach is take here i.e. air pollutants in general are considered. The first chapter presents a brief introduction to the need and scope of air pollution dispersion modelling. The second chapter is a very important chapter discussing the aspects of meteorology relevant to air pollution and dispersion modelling. This chapter is important because without this information one really does not understand the phenomena affecting dispersion, the scope and applicability of various models or their limitations under various weather and site conditions. The third chapter discusses the air pollution models in detail. These models are applicable to distances of a few tens of kilometres. The fourth chapter discusses the various aspects of meteorological measurements relevant to air pollution. The chapters are followed by two appendices. Apendix A discusses the reliability of air pollution estimates. Apendix B gives some practical examples relevant to general air pollution. It is hoped that the document will prove very useful to the users. (author)

Climate risks by radioactive krypton-85 from nuclear fission. Atmospheric-electrical and air-chemical effects of ionizing radiation in the atmosphere

International Nuclear Information System (INIS)

Kollert, R.

1994-01-01

The study shows that krypton-85 from nuclear fission enhances air ionization and, thus, interferes with the atmospheric-electrical system and the water balance of the earth atmosphere. This is reason for concern: There are unforeseeable effects for weather and climate if the krypton-85 content of the earth atmosphere continues to rise. There may be a krypton-specific greenhouse effect and a collapse of the natural atmospheric-electrical field. In addition, human well-being may be expected to be impaired as a result of the diminished atmospheric-electrical field. There is also the risk of radiochemical actions and effects caused-by krypton-85-containing plumes in other air-borne pollutants like the latters' transformation to aggressive oxidants. This implies radiation smog and more acid rain in the countries exposed. This study summarizes findings gained in these issues by various sciences, analyses them and elaborates hypotheses on the actions and effects of krypton-85 on the air, the atmosphere and the climate. (orig./HP) [de

Safety-related control air systems - approved 1977

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

HTR-TN achievements and prospects for future developments

International Nuclear Information System (INIS)

Hittner, D.; Angulo, C.; Basini, V.; Bogusch, E.; Breuil, E.; Buckthorpe, D.; Chauvet, V.; Futterer, M.A.; Van Heek, A.; Von Lensa, W.; Yvon, P.

2011-01-01

It is already 10 years since the (European) High Temperature Reactor Technology Network (HTR-TN) launched a program for development of HTR technology, which expanded through three successive Euratom framework programs, with many projects in line with the network strategy. Widely relying in the beginning on the legacy of the former European HTR developments (DRAGON, AVR, THTR, etc.) that it contributed to safeguard, this program led to advances in HTR/VHTR technologies and produced significant results, which can contribute to the international cooperation through Euratom involvement in the Generation IV International Forum (GIF). the main achievements of the European program, performed in complement to efforts made in several European countries and other GIF partners, are presented: they concern the validation of computer codes (reactor physics, as well as system transient analysis from normal operation to air ingress accident and fuel performance in normal and accident conditions), materials (metallic materials for vessel, direct cycle turbines and intermediate heat exchanger, graphite, etc.), component development, fuel manufacturing and irradiation behavior, and specific HTR waste management (fuel and graphite). Key experiments have been performed or are still ongoing, like irradiation of graphite and of fuel material (PYCASSO experiment), high burn-up fuel PIE, safety test and isotopic analysis, IHX mock-up thermohydraulic test in helium atmosphere, air ingress experiment for a block type core, etc. Now HTR-TN partners consider that it is time for Europe to go a step forward toward industrial demonstration. In line with the orientations of the 'Strategic Energy Technology Plan (SET-Plan)' recently issued by the European Commission that promotes a strategy for development of low-carbon energy technologies and mentions Generation IV nuclear systems as part of key technologies, HTR-TN proposes to launch a program for extending the contribution of nuclear energy to

Modular head assembly and method of retrofitting existing nuclear reactor facilities

International Nuclear Information System (INIS)

Malandra, L.J.; Ledue, R.J.; Hankinson, M.F.; Kowalski, E.F.

1987-01-01

A method is described of retrofitting existing nuclear reactor facilities so as to form a modular closure head assembly for a nuclear reactor pressure vessel, where the existing nuclear reactor facilities comprise control rod drive mechanism cooling systems which include vertically extending elbow air ducts inter-connecting vertically spaced upper and lower air manifolds. The elbow air ducts extend radially beyond the peripheral envelope of the closure head, comprising the steps of: removing the upper air manifold; removing the vertically extending elbow air ducts; capping the air ports of the lower air manifold which ports were previously fluidically connecting the lower air manifold to the vertically extending elbow air ducts; disposing vertically upwardly extending air exhaust ducts above the lower air manifold in such an manner that the air exhaust ducts are disposed within the peripheral envelope of the closure head; fluidically connecting exhaust fans to the upper regions of the air exhaust ducts; fluidically connecting the lower regions of the air exhaust ducts the lower air manifold; permanently securing lift rods to the closure head at positions disposed radially outwardly of the lower air manifold; attaching a seismic support platform to the lift rods; proving fluidic passage of the vertically extending air exhaust ducts through the seismic support platform; attaching a missile shield plate to the lift rods; and proving fluidic passage of the vertically extending air exhaust ducts through the missile shield plate

131I concentrations in air, milk and antelope thyroids in southeastern Idaho

International Nuclear Information System (INIS)

Markham, O.D.; Halford, D.K.; Bihl, D.E.

1980-01-01

Iodine-131 concentrations were determined in air, milk, and antelope (Antilocapra americana) thyroids from southeastern Idaho during 1972-77. Samples were collected in the vicinity of the Idaho National Engineering Laboratory Site which has 17 operating nuclear reactors, a fuel reprocessing plant, and a nuclear waste management facility. Samples were also collected from control areas. During the study, fallout occurred from five People's Republic of China above-ground nuclear weapon detonations. All 131 I detected in air and milk samples was attributed to fallout from the Chinese nuclear tests. 131 I was detected in low-volume air samples following only one of the five detonations while 131 I was detected in milk following four of the detonations. 131 I occurred in antelope thyroids during all five of the fallout periods and following at least one atmospheric release from facilities at the Idaho National Engineering Laboratory Site. Thyroids were the most sensitive indicators of 131 I in the environment followed by milk and then air. Maximum concentrations in thyroids, milk, and air were 400, 20 and 4 times higher respectively than their respective detection limits. (author)

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

Energy Technology Data Exchange (ETDEWEB)

Aldape U, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-10-15

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

Modeling of thermal evolution of near field area around single pit mode nuclear waste canister disposal in soft rocks

International Nuclear Information System (INIS)

Bajpai, R.K.; Verma, A.K.; Maheshwar, Sachin

2016-01-01

Soft rocks like argillites/shales are under consideration worldwide as host rock for geological disposal of vitrified as well as spent fuel nuclear waste. The near field around disposed waste canister at 400-500m depth witnesses a complex heat field evolution due to varying thermal characteristics of rocks, coupling with hydraulic processes and varying intensity of heat flux from the canister. Smooth heat dissipation across the rock is desirable to avoid buildup of temperature beyond design limit (100 °C) and resultant micro fracturing due to thermal stresses in the rocks and intervening buffer clay layers. This also causes enhancement of hydraulic conductivity of the rocks, radionuclide transport and greater groundwater ingress towards the canister. Hence heat evolution modeling constitutes an important part of safety assessment of geological disposal facilities

Study on HVAC system in nuclear facility

International Nuclear Information System (INIS)

Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

2003-01-01

Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

Method to increase the safety of a final storage site in a salt cavern filled with solidified radioactive waste with regard to unforeseen rock movements and/or water ingress into cavities of the final storage site

International Nuclear Information System (INIS)

Koester, R.; Rudolph, G.; Kroebel, R.

1986-01-01

The wastes of weak or average radio-activity (e.g. T) are stored in barrels in a salt mine. In order to prevent leaching of the waste after the ingress of water into the salt mine, the intermediate spaces between the barrels are filled with a concrete grout. This grout consists of a water/bentonite/cement mixture, to which sand may be added, and which hardens. It forms a monolithic block. (orig./PW)

Method to increase the safety of a final storage site in a salt cavern filled with solidified radioactive waste with regard to unforeseen rock movements and/or water ingress into cavities of the final storage site

International Nuclear Information System (INIS)

Koester, R.; Rudolph, G.; Kroebel, R.

1980-01-01

The wastes of weak or average radio-activity (e.g. T) are stored in barrels in a salt mine. In order to prevent leaching of the waste after the ingress of water into the salt mine, the intermediate spaces between the barrels are filled with a concrete grout. This grout consists of a water/bentonite/cement mixture, to which sand may be added, and which hardens. It forms a monolithic block. (DG) [de

Wear Behavior of Selected Nuclear Grade Graphites at Room Temperature in Ambient Air Environment

International Nuclear Information System (INIS)

Kim, Eung-Seon; Park, Kwang-Seok; Kim, Yong-Wan

2008-01-01

In a very high temperature reactor (VHTR), graphite will be used not only for as a moderator and reflector but also as a major structural component due to its excellent neutronic, thermal and mechanical properties. In the VHTR, wear of graphite components is inevitable due to a neutron irradiation-induced dimensional change, thermal gradient, relative motions of graphite components and a shock load such as an earthquake. Large wear particles accumulated at the bottom of a reactor can influence the cooling of the lower part and small wear particles accumulated on the primary circuit and heat exchanger tube can make it difficult to inspect the equipment, and also decrease the heat exchange rate. In the present work, preliminary wear tests were performed at room temperature in ambient air environment to understand the basic wear characteristics of selected nuclear grade graphites for the VHTR

Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release; Comportement accidentel du combustible nucleaire dans un site d'entreposage sous air: Etude de l'oxydation de la ceramique nucleaire et du relachement des gaz de fission

Energy Technology Data Exchange (ETDEWEB)

Desgranges, L.

2006-12-15

After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO{sub 2} oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO{sub 2} to U{sub 3}O{sub 7}, and from U{sub 3}O{sub 7} to U{sub 3}O{sub 8}), and with further high activity laboratory experiments

New challenges to air/gas cleaning systems

Energy Technology Data Exchange (ETDEWEB)

Kovach, J.L. [NUCON International, Inc., Columbus, OH (United States)

1997-08-01

This paper discusses the need for changes in the design and manufacturing of air and gas cleaning systems to meet waste management and site remediation requirements. Current design and manufacturing practices are primarily directed toward evaluating operational problems with existing systems in nuclear reactor facilities. However, nuclear waste management needs have developed which are much broader in scope and have different processing conditions. Numerous examples of air cleaning needs for waste management activities are provided; the major differences from operating facility needs are the requirement for continuous effluent treatment under widely different processing conditions. Related regulatory issues are also discussed briefly. 1 ref.

8. Peaceful uses of nuclear explosions

International Nuclear Information System (INIS)

Musilek, L.

1992-01-01

The chapter deals with peaceful uses of nuclear explosions. Described are the development of the underground nuclear explosion, properties of radionuclides formed during the explosion, their distribution, the release of radioactive products of underground nuclear explosions into the air, their propagation in the atmosphere, and fallout in the landscape. (Z.S.). 1 tab., 8 figs., 19 refs

Air conditioning device for pool facilities in nuclear power plant buildings

International Nuclear Information System (INIS)

Taruishi, Yoshiaki; Ishida, Seiji.

1981-01-01

Purpose: To improve the temperature and humidity conditions for the working circumstance, prevent condensations on the wall surface and enable the reduction in the irradiation exposure to workers. Constitution: Air intake ports are provided on the side wall of a fuel storage pool or an equipment installation pool above the water level and connected by way of their exhaust ducts to the exhaust ducts of an air ventilation system. While on the other hand, air feed ducts having horizontally opened blowing ports and air exhaust ducts having horizontally opened exhaust ports above and in adjacent to the air feed ducts are provided on the side walls of the pool buildings at the height near the floor level. With this structure, fresh outdoor airs blown out horizontally from the blowing ports provided near the floor level can improve the temperature and humidity conditions of the working circumstance for the workers working on the floor. Further, an air clean up device is provided to the feed and exhaust systems for clean up the feed and exhaust airs. (Furukawa, Y.)

Seismic evaluation of nuclear installations

International Nuclear Information System (INIS)

Mattar Neto, Miguel

1997-01-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

Controlled air pyrolysis incinerator

International Nuclear Information System (INIS)

Dufrane, K.H.; Wilke, M.

1982-01-01

An advanced controlled air pyrolysis incinerator has been researched, developed and placed into commercial operation for both radioactive and other combustible wastes. Engineering efforts cocentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced a minimum amount of secondary waste. Feed material is continuously fed by gravity into the system's pyrolysis chamber without sorting, shredding, or other such pretreatment. Metal objects, liquids such as oil and gasoline, or solid products such as resins, blocks of plastic, tire, animal carcasses, or compacted trash may be included along with normal processed waste. The temperature of the waste is very gradually increased in a reduced oxygen atmosphere. Volatile pyrolysis gases are produced, tar-like substances are cracked and the resulting product, a relatively uniform, easily burnable material, is introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gasthen passing through a simple dry clean-up system. Gas temperatures are then reduced by air dilution before passing through final HEPA filters. Both commercial and nuclear installations have been operated with the most recent application being the central incinerator to service West Germany's nuclear reactors

Water-ingress analysis for the 200 MWe pebble-bed modular high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Zheng Yanhua; Shi Lei; Wang Yan

2010-01-01

Water ingress into the primary circuit is generally recognized as one of the severe accidents with potential hazard to the modular high temperature gas-cooled reactor adopting steam-turbine cycle, which will cause a positive reactivity introduction, as well as the chemical corrosion of graphite fuel elements and reflector structure material. Besides, increase of the primary pressure may result in the opening of the safety valves, consequently leading the release of radioactive isotopes and flammable water gas. The analysis of such a kind of important and particular accident is significant to verify the inherent safety characteristics of the modular HTR plants. Based on the preliminary design of the 200 MWe high temperature gas-cooled reactor pebble-bed modular (HTR-PM), the design basis accident of a double-ended guillotine break of one heating tube and the beyond design basis accident of a large break of the main steam collection plate have been analyzed by using TINTE code, which is a special transient analysis program for high temperature gas-cooled reactors. Some safety relevant concerns, such as the fuel temperature, the primary loop pressure, the graphite corrosion, the water gas releasing amount, as well as the natural convection influence on the condition of failing to close the blower flaps, have been studied in detail. The calculation results indicate that even under some severe hypothetical postulates, the HTR-PM is able to keep the inherent safeties of the modular high temperature gas-cooled reactor and has a relatively good natural plant response, which will not result in environmental radiation hazard.

Experience of oil in CANDU moderator during A831 planned outage at Bruce Power

International Nuclear Information System (INIS)

Ma, G.; Nashiem, R.; Matheson, S.; Stuart, C.; Roberts, J.G.

2011-01-01

In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

Experience of oil in CANDU® moderator during A831 planned outage at Bruce Power

International Nuclear Information System (INIS)

Ma, G.; Nashiem, R.; Matheson, S.; Stuart, C.; Roberts, J.G.

2010-01-01

In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU® reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

Experience of oil in CANDU® moderator during A831 planned outage at Bruce Power

Energy Technology Data Exchange (ETDEWEB)

Ma, G.; Nashiem, R.; Matheson, S. [Bruce Power, Tiverton, Ontario (Canada); Stuart, C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Roberts, J.G. [CANTECH Associates Ltd., Burlington, Ontario (Canada)

2010-07-01

In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU® reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

Experience of oil in CANDU moderator during A831 planned outage at Bruce Power

Energy Technology Data Exchange (ETDEWEB)

Ma, G.; Nashiem, R.; Matheson, S. [Bruce Power, Tiverton, Ontario (Canada); Stuart, C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Roberts, J.G. [CANTECH Associates Ltd., Burlington, Ontario (Canada)

2011-03-15

In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

Development of a method to measure the concentration of 14C in the stack air of nuclear power plants by accelerator mass spectrometry (AMS)

International Nuclear Information System (INIS)

Stenstroem, K.; Erlandsson, B.; Hellborg, R.; Haakansson, K.; Wiebert, A.; Skog, G.

1993-04-01

C-14, a pure low-energetic beta-emitter, is produced through various nuclear reactions in nuclear power plants. Some of this C-14 is air-borne and is transported via the ventilation system through the stack of the power station and is integrated in living matter in the surroundings of the plant. The long half-life of the isotope (T1/2=5730 years) and the biological importance of carbon may lead to a not negligible contribution of the radiation dose for those living in the neighbourhood of nuclear power plants. C-14 has earlier been measured radiometrically with mainly two different methods, using proportional counters or liquid scintillators. In this report a new method is described, using an accelerator based technique. accelerator mass spectrometry (AMS). This technique has at least three advantages over the radiometrical methods. It requires only a few litres of gas per sample, which is 100-1000 times less compared to the radiometrical methods. It is insensitive to the beta and gamma rays from other radioactive isotopes in the stack air. The measuring time with AMS, about 20 minutes per sample, is considerably shorter compared to the radiometrical methods, which demand several hours per sample. The integrity of the AMS method is high and it might be convenient for regulatory supervision. (22 refs.)

Radionuclides in ground-level air

International Nuclear Information System (INIS)

Sinkko, K.

1987-01-01

In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

Nuclear industry technology boomerang

International Nuclear Information System (INIS)

Scholler, R.W.

1987-01-01

The benefits to the medical, pharmaceutical, semiconductor, computer, video, bioscience, laser, defense, and numerous high-tech industries from nuclear technology development fallout are indeed numerous and increase every day. Now those industries have made further progress and improvements that, in return, benefit the nuclear industry. The clean-air and particle-free devices and enclosures needed for protection and decontamination are excellent examples

Nuclear war hazards

International Nuclear Information System (INIS)

Chazov, E.I.; Il'in, L.A.; Gus'kova, A.K.

1982-01-01

An attempt is made to forecast medical and bilogical and aftereffects of nuclear weapons application in a number of situations. In particular, the effects of a single high-yield air or surface nuclear explosion on a city with 1 mln population are considered as well as the aftereffects of the exposure of human beings to local radioactive fallouts outside the ground zero of a surface nuclear explosion. The aftereffects for the population of local and global radioactive fallouts caused by the realization of one of the adopted in the West variants of mass nuclear strives exchange between the hostile sides are estimated. Certain aspects of medical and biological aftereffects of neutron weapons application are discussed

The Defense Science Board Permanent Task Force on Nuclear Weapons Surety. Report on the Unauthorized Movement of Nuclear Weapons

National Research Council Canada - National Science Library

Welch, Larry D; Agnew, Harold M; Bien, Lyle G; Crawford, John C; Foster, Jr., John S; Gold, Sydell P; McCarthy, James P; Mies, Richard W; Neary, Thomas H; Selden, Robert L

2008-01-01

...]) and the Commander, U.S. Strategic Command to conduct an independent investigation of the unauthorized transfer of nuclear warheads between Minot Air Force Base, North Dakota, and Barksdale Air Force Base, Louisiana on 30 August 2007...

Qualification of box HEPA filters for nuclear applications

International Nuclear Information System (INIS)

Bergman, W.; Larsen, G.; Wilson, K.; Rainer, F.

1995-03-01

We have successfully completed qualification tests on high efficiency particulate air (HEPA) filters that are encapsulated within a box and manufactured by American Air Filters. The qualification tests are required by the American Society of Mechanical Engineers Standard ASME N509 and the U.S. Military Standard MIL-F-51068 for HEPA filters to be used in nuclear applications. The qualification tests specify minimum filter efficiencies following exposure to heated air, overpressure, and rough handling. Prior to this study, no box HEPA filters from any manufacturer had been qualified despite their wide-spread use in Department of Energy (DOE) facilities. Box HEPA filters are not addressed in any of the existing HEPA standards and only briefly discussed in the Nuclear Air Cleaning Handbook

New developments in the air transport of plutonium

International Nuclear Information System (INIS)

Andersen, J.A.

1978-01-01

A new package for the air transport of plutonium has been developed in response to a United States Public Law which restricts the U.S. air transport of plutonium except for small medical devices. This new package, called PAT-1 for plutonium air transportable package model 1, is the result of the NRC-sponsored (NRC=U.S. Nuclear Regulatory Commission.) PARC (plutonium accident resistant container) project at Sandia Laboratories, Albuquerque. The PAT-1 package is designed to meet or exceed new criteria specified in NUREG-0360. These inclued a severe test sequence of impact (>250 knots) on an unyielding target, crush, puncture, slash, a large JP-4 fire for 1 hour, followed by water immersion, with stringent acceptance standards on plutonium release, nuclear shielding, and nuclear criticality. The PAT-1 package design features a high energy absorption capability with high-level fire protection. It weighs approximately 227 kg (500 lb) when loaded with 2 kg PuO 2 , and can accommodate up to 25 watts thermal energy from the plutonium load

Review of the environmental impact of nuclear energy

Energy Technology Data Exchange (ETDEWEB)

El-Hinnawi, E E

1978-04-01

The radioactivity released from the products of nuclear fission is the main focus of public concern about the expansion in the use of nuclear power despite stringent control measures and precautions taken. Environmental impacts associated with all the steps in the nuclear fuel cycle are examined. Discussed are: uranium mining and milling, manufacture of fuel elements for the reactor, transport and reprocessing of irradiated fuel, reactor operation, and management of wastes produced in the cycle. Environmental impacts of a coal-fired power plant are compared with impacts of three nuclear plants with the same generating capacities. Impacts compared are thermal heat waste, effluent radioactivity, air pollution, radioactive and ash waste products, and land used for the plant. The environmental advantages of the nuclear reactors occur in the categories of air pollutant effluents and land used for plants. (45 references, 3 tables)

Effects of welding fumes on nuclear air cleaning system carbon adsorber banks

Energy Technology Data Exchange (ETDEWEB)

Roberson, P.W. [Duke Power Company, Huntersville, NC (United States)

1997-08-01

Standard Technical Specifications for nuclear air cleaning systems include requirements for surveillance tests following fire, painting, or chemical release in areas communicating with the affected system. To conservatively implement this requirement, many plants categorize welding as a chemical release process, and institute controls to ensure that welding fumes do not interact with carbon adsorbers in a filter system. After reviewing research data that indicated welding had a minimal impact on adsorber iodine removal efficiency, further testing was performed with the goal of establishing a welding threshold. It was anticipated that some quantity of weld electrodes could be determined that had a corresponding detrimental impact on iodine removal efficiency for the exposed adsorber. This value could be used to determine a conservative sampling schedule that would allow the station to perform laboratory testing to ensure system degradation did not occur without a full battery of surveillance tests. A series of tests was designed to demonstrate carbon efficiency versus cumulative welding fume exposure. Three series of tests were performed, one for each of three different types of commonly used weld electrodes. Carbon sampling was performed at baseline conditions, and every five pounds of electrode thereafter. Two different laboratory tests were performed for each sample; one in accordance with ASTM 3803/1989 at 95% relative humidity and 30 degrees C, and another using the less rigorous conditions of 70% relative humidity and 80 degrees C. Review of the test data for all three types of electrodes failed to show a significant correlation between carbon efficiency degradation and welding fume exposure. Accordingly, welding is no longer categorized as a `chemical release process` at McGuire Nuclear Station, and limits on welding fume interaction with ventilation systems have been eliminated. 4 refs., 3 figs., 1 tab.

Isopleths of surface air concentration and surface air kerma rate due to a radioactive cloud released from a stack (3)

International Nuclear Information System (INIS)

Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori

2004-06-01

This report is a revised edition of 'Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II) '(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) instead of Air Absorbed Dose Rate (Gy/h), and the record of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer. (author)

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques

International Nuclear Information System (INIS)

Aldape U, F.

1993-10-01

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

First report of the Civil Nuclear Power Working Group to the Technical Comittee of the National Society for Clean Air -Summer 1988

International Nuclear Information System (INIS)

1988-01-01

The accident at the Chernobyl reactor in April 1986 had serious consequences, not just for Russia but for many countries in Europe. Following the accident, the National Society for Clean Air formed a Working Group to look at the Society's policy on civil nuclear power. Its finding and recommendations are presented in this first report. The subject was considered under several headings - radioactivity (public education in measurement and dose evaluation), emergency procedures in the event of incidents overseas, radiation monitoring, a national monitoring and information service, plant safety, nuclear materials handling and radioactive waste disposal, energy policy and conservation. Four main recommendations are made on public education, risk assessment and radiation monitoring, radioactive waste disposal and energy policy. (U.K.)

Tritium as an indicator of venues for nuclear tests.

Science.gov (United States)

Lyakhova, O N; Lukashenko, S N; Mulgin, S I; Zhdanov, S V

2013-10-01

Currently, due to the Treaty on the Non-proliferation of Nuclear Weapons there is a highly topical issue of an accurate verification of nuclear explosion venues. This paper proposes to consider new method for verification by using tritium as an indicator. Detailed studies of the tritium content in the air were carried in the locations of underground nuclear tests - "Balapan" and "Degelen" testing sites located in Semipalatinsk Test Site. The paper presents data on the levels and distribution of tritium in the air where tunnels and boreholes are located - explosion epicentres, wellheads and tunnel portals, as well as in estuarine areas of the venues for the underground nuclear explosions (UNE). Copyright © 2013 Elsevier Ltd. All rights reserved.

Radioactive air sampling methods

CERN Document Server

Maiello, Mark L

2010-01-01

Although the field of radioactive air sampling has matured and evolved over decades, it has lacked a single resource that assimilates technical and background information on its many facets. Edited by experts and with contributions from top practitioners and researchers, Radioactive Air Sampling Methods provides authoritative guidance on measuring airborne radioactivity from industrial, research, and nuclear power operations, as well as naturally occuring radioactivity in the environment. Designed for industrial hygienists, air quality experts, and heath physicists, the book delves into the applied research advancing and transforming practice with improvements to measurement equipment, human dose modeling of inhaled radioactivity, and radiation safety regulations. To present a wide picture of the field, it covers the international and national standards that guide the quality of air sampling measurements and equipment. It discusses emergency response issues, including radioactive fallout and the assets used ...

Review of nuclear air treatment system related License Event Reports for the period 1985 - 1987

International Nuclear Information System (INIS)

Jacox, J.W.

1989-01-01

This paper will continue the review of HVAC/NATS related LERS presented at past Air Cleaning Conferences by Dr. D. W. Moeller and his associates. The general approach and format are similar. LER abstracts from mid 1985 through 1987 were reviewed and those related to HVAC/NATS classified and analyzed. The categories were jointly developed by Dr. Moeller, Dr. Casper Sun and myself. In appropriate cases both primary and secondary categories fora problem are given. A basic listing by category and brief statistical review are presented. Additionally a number of categories are discussed in some detail. The categories chosen for specific review are intended to highlight particular problem areas. NUREG/CR-2000 License Event Report (LER) Compilation is the basis for the initial review and coding. In essentially all cases where an LER is classified as of interest the complete LER was obtained and reviewed in full. The intent of this paper is to provide a basis for the industry to document and analyze problem areas that require additional attention. It appears that about 15% of all LERS in the subject period are HVAC/NATS related. This figure is generally consistent with those reported at the 17th DOE Nuclear Air Cleaning Conference. It is hoped that such attention will allow additional resources to be allocated to upgrade systems, procedures and training as well as in some cases government regulation

Lin's theory of flux and nuclear reactions

International Nuclear Information System (INIS)

Ping-Wha Lin

2002-01-01

Mathematical development of Lin's theory of flux is presented. Based on the Theory, when a chemical reaction system is subjected to a high time rate of temperature change, it changes from equilibrium to non-equilibrium conditions. It is proved mathematically that, when a gas system is subjected to a high time rate of temperature increase, the activities of particles (molecules, atoms or nuclei, and electrons) are increased: the particles are accelerated; frequencies and amplitudes of electron and atomic vibrations in a molecule increased; average kinetic energy of the particles increased; atomic bonds are ruptured; electrons are caused to leave their orbits. If most or all of the electrons leave their orbits, the gas fluid becomes plasma, which is very active chemically. The acceleration of nuclei in the dynamic condition can lead to nuclear reactions. In the pilot plant studies conducted at Research Triangle, NC, USA, for SO 2 conversion to SO 3 by rapid heating, a 10-ft high vertically fired combustor (VFC) was used. Air containing 0.5% SO 2 is forced continuously through the VFC, where it is heated by burners for conversion of SO 2 to SO 3 . During the idle period of operation, no external heat is added to the system by turning off the burners. It is observed that, as the air passing through the VFC during the idle period of sixteen hours, the temperature of the flowing air consistently rises up rapidly from ambient temperature (90 deg F) at inlet of the VFC to an average temperature as high as 582 deg F (in the range of 840 deg F to 455 deg F) at one section of the VFC, an increase of about 500 deg F. The air flow temperature increase of such large magnitude and long duration clearly indicates that nuclear reactions are present in VFC. It is also found that the water vapour in the air stream has completely disappeared in the VFC, for no sulphuric acid formation resulting from the reaction of water and SO 3 is detected there. Presumably, the water vapour in the

Risk assessment of intake of foods and soil, and air radiation dose after Fukushima Daiichi nuclear disaster

International Nuclear Information System (INIS)

Fujinaga, Aiichiro; Yoneda, Minoru; Ikegami, Maiko

2012-01-01

Risk assessment of soil contaminated with radionuclides, due to the accident of Fukushima nuclear power plant after the earthquake on March 11, 2011, was carried out by considering consumption of the contaminated food. The exposure routes were set as food intake, ingestion and inhalation of soil particles, and external radiation from the ground. As a result, exposures by ingestion, and inhalation of soil particles were negligible, and exposure by food intake and external exposure from the ground were comparatively large. This study shows air dose by the accident should be under 0.2 μSv/hour in order to control the radiation dose with consumption of food under 1 μSv/year. (author)

A Dynamic Model for Roll Motion of Ships Due to Flooding

DEFF Research Database (Denmark)

Xia, Jinzhu; Jensen, Jørgen Juncher; Pedersen, Preben Terndrup

1997-01-01

A dynamic model is presented of the roll motion of damaged RoRo vessels which couples the internal cross-flooding flow and the air action in the equalizing compartment. The cross flooding flow and the air motion are modelled by a modified Bernoulli equation, where artificial damping is introduced...... to avoid modal instability based on the original Bernoulli equation. The fluid action of the flooded water on the ship is expressed by its influence on the moment of inertia of the ship and the heeling moment, which is a couple created by the gravitational force of the flooded water and the change...... of buoyancy of the ship.Two limiting flooding cases are examined in the present analysis: The sudden ingress of a certain amount of water to the damaged compartment with no further water exchange between the sea and the flooded compartment during the roll motion, and the continuous ingress of water through...

[Measures against Radiation Exposure Due to Large-Scale Nuclear Accident in Distant Place--Radioactive Materials in Nagasaki from Fukushima Daiichi Nuclear Power Plant].

Science.gov (United States)

Yuan, Jun; Sera, Koichiro; Takatsuji, Toshihiro

2015-01-01

To investigate human health effects of radiation exposure due to possible future nuclear accidents in distant places and other various findings of analysis of the radioactive materials contaminating the atmosphere of Nagasaki due to the Fukushima Daiichi Nuclear Power Plant accident. The concentrations of radioactive materials in aerosols in the atmosphere of Nagasaki were measured using a germanium semiconductor detector from March 2011 to March 2013. Internal exposure dose was calculated in accordance with ICRP Publ. 72. Air trajectories were analyzed using NOAA and METEX web-based systems. (134)Cs and (137)Cs were repeatedly detected. The air trajectory analysis showed that (134)Cs and (137)Cs flew directly from the Fukushima Daiichi Nuclear Power Plant from March to April 2011. However, the direct air trajectories were rarely detected after this period even when (134)Cs and (137)Cs were detected after this period. The activity ratios ((134)Cs/(137)Cs) of almost all the samples converted to those in March 2011 were about unity. This strongly suggests that the (134)Cs and (137)Cs detected mainly originated from the Fukushima Daiichi Nuclear Power Plant accident in March 2011. Although the (134)Cs and (137)Cs concentrations per air volume were very low and the human health effects of internal exposure via inhalation is expected to be negligible, the specific activities (concentrations per aerosol mass) were relatively high. It was found that possible future nuclear accidents may cause severe radioactive contaminations, which may require radiation exposure control of farm goods to more than 1000 km from places of nuclear accidents.

Ex-vacuo nuclear reaction analysis of deuterium

International Nuclear Information System (INIS)

Lee, S.R.; Doyle, B.L.

1989-01-01

A novel technique for performing in-air d( 3 He, p) nuclear reaction analysis of deuterium using external 3 He ion beams ranging in energy from 0.3-2.0 MeV is presented. Variable on-target beam energies for the depth profiling of deuterium are obtained by varying the transmission distance of the external 3 He beam in air. The ex-vacuo nuclear reaction analysis (XNRA) apparatus is described, and unique aspects and limitations of in-air depth profiling of deuterium using the d( 3 He, p) reaction are discussed. Example analyses where XNRA has been used for the multidimensional measurement of deuterium in fusion reactor components are presented in order to illustrate the advantages of XNRA for deuterium. These advantages include nondestructive analysis of large targets, efficient depth profiling via variable air gap energy tuning, and rapid analysis of numerous samples in the absence of vacuum cycling. (orig.)

Air Monitoring to Control the Intake of Airborne Radioiodine-131 Contaminants by Nuclear Medicine Workers

International Nuclear Information System (INIS)

Jiemwutthisak, P.; Sritongkul, N.; Chaudakshetrin, P.; Kanchanaphiboon, P.; Tuntawiroon, M.

2012-01-01

Inhalation of radioiodine-131 is the largest cause of internal dose to nuclear medicine workers. The concentration of radioiodine-131 in air is limited by the Derived Air Concentration (DAC) of 416.67 Bq/m3. In this study air monitoring shall be performed to measure the radioiodine-131 contaminant in air by sample collection and analysis. Air samples were drawn from areas where there is a potential for I-131 airborne radioactivity e.g. in the hot laboratory, radioiodine treatment rooms, radioactive waste collection areas and waste water treatment plant. A portable battery-operated air sampler, Gilian BDX II with carbon- impregnated cellulose filters was used for air sampling. The flow rate was adjusted to 3 liters per minute and the sampler run for 180 minutes. Iodine-131 radioactivity on filter was measured for 10 minutes by 2 NaI(Tl) gamma counters, Perkin Elmer Wallac Wizard 1480 (3''x3'') and Atomlab 950 PC (2''x2'') with and objective for inter comparison. Counting efficiency of the counters are 57 and 39 percent respectively. Agreeable results of I-131 radioactivity were obtained from both gamma counters. The mean I-131 concentrations measured by Wallac(Atomlab) were 31.59±16.31 (29.84±14.74) Bq/m 3 in radioiodine fume hood for treatment dose dispensing, 8.98±4.33 (7.58±5.10) Bq/m 3 in fume hood accommodated with a dose calibrator, 7.80±5.39 (7.54±5.04) Bq/m 3 in radioactive waste storage area, 0.03±0.54 (0.03±0.57) Bq/m 3 in patient waiting area, 2.94±3.60 (2.55±2.98) Bq/m 3 in hospital ward waste collection area and 0.03±0.01 (0.03±0.01) Bq/m 3 in the water treatment plant area. Radioiodine concentrations in patient's room increases linearly as the administered dose was increasing. Mean±SD of the measured concentrations were 11.63±9.30 (9.86±8.98) Bq/m 3 , 18.57±13.24 (17.35±12.33) Bq/m 3 and 31.90±22.32 (30.90±22.49) Bq/m 3 for the administered doses of 3.7, 5.55 and 7.4 Bq respectively. Radioiodine concentrations in all specified areas

Ruthenium release modelling in air and steam atmospheres under severe accident conditions using the MAAP4 code

International Nuclear Information System (INIS)

Beuzet, Emilie; Lamy, Jean-Sylvestre; Perron, Hadrien; Simoni, Eric; Ducros, Gérard

2012-01-01

Highlights: ► We developed a new modelling of fuel oxidation and ruthenium release in the EDF version of the MAAP4 code. ► We validated this model against some VERCORS experiments. ► Ruthenium release prediction quantitatively and qualitatively well reproduced under air and steam atmospheres. - Abstract: In a nuclear power plant (NPP), a severe accident is a low probability sequence that can lead to core fusion and fission product (FP) release to the environment (source term). For instance during a loss-of-coolant accident, water vaporization and core uncovery can occur due to decay heat. These phenomena enhance core degradation and, subsequently, molten materials can relocate to the lower head of the vessel. Heat exchange between the debris and the vessel may cause its rupture and air ingress. After lower head failure, steam and air entering in the vessel can lead to degradation and oxidation of materials that are still intact in the core. Indeed, Zircaloy-4 cladding oxidation is very exothermic and fuel interaction with the cladding material can decrease its melting temperature by several hundred of Kelvin. FP release can thus be increased, noticeably that of ruthenium under oxidizing conditions. Ruthenium is of particular interest because of its high radio-toxicity due to 103 Ru and 106 Ru isotopes and its ability to form highly volatile compounds, even at room temperature, such as gaseous ruthenium tetra-oxide (RuO 4 ). It is consequently of great need to understand phenomena governing steam and air oxidation of the fuel and ruthenium release as prerequisites for the source term issues. A review of existing data on these phenomena shows relatively good understanding. In terms of oxygen affinity, the fuel is oxidized before ruthenium, from UO 2 to UO 2+x . Its oxidation is a rate-controlling surface exchange reaction with the atmosphere, so that the stoichiometric deviation and oxygen partial pressure increase. High temperatures combined with the presence

Measurement of volumic activities of radon in air in houses and in working rooms with solid state nuclear track detectors

International Nuclear Information System (INIS)

Hakam, O.K.

1993-01-01

In this work, a new method of measuring volumic activity of radon has been developed. This method is based on using solid state nuclear track detectors LR-115 type II. It has been applied to measurement of volumic activities of radon in air in houses and in working rooms in different regions of Morocco. These measurements, carried out for the first time in the country, allowed to estimate the dose equivalents of radon received by the population of the studied regions. 59 refs., 38 figs., 38 tabs. (F.M.)

Diaphragms in air-operated valves

Energy Technology Data Exchange (ETDEWEB)

Groeger, J.E.

1996-12-01

The author will present current issues related to diaphgrams in air-operated valves. Altran Materials Engineering, Inc., often performs root-cause analyses for nuclear power plant owners. The author will discuss various analyses that have been performed or are currently underway.

Ventilating system for reprocessing of nuclear fuel rods

International Nuclear Information System (INIS)

Szulinski, M.J.

1981-01-01

In a nuclear facility such as a reprocessing plant for nuclear fuel rods, the central air cleaner discharging ventilating gas to the atmosphere must meet preselected standards not only as to the momentary concentration of radioactive components, but also as to total quantity per year. In order to comply more satisfactorily with such standards, reprocessing steps are conducted by remote control in a plurality of separate compartments. The air flow for each compartment is regulated so that the air inventory for each compartment has a slow turnover rate of more than a day but less than a year, which slow rate is conveniently designated as quasihermetic sealing. The air inventory in each such compartment is recirculated through a specialized processing unit adapted to cool and/or filter and/or otherwise process the gas. Stale air is withdrawn from such recirculating inventory and fresh air is injected (eg., By the less than perfect sealing of a compartment) into such recirculating inventory so that the air turnover rate is more than a day but less than a year. The amount of air directed through the manifold and duct system from the reprocessing units to the central air cleaner is less than in reprocessing plants of conventional design

An Accelerated Test Method of Simultaneous Carbonation and Chloride Ion Ingress: Durability of Silica Fume Concrete in Severe Environments

Directory of Open Access Journals (Sweden)

S. A. Ghahari

2016-01-01

Full Text Available The effects of simultaneous carbonation and chloride ion attack on mechanical characteristics and durability of concrete containing silica fume have been investigated through an accelerated test method. Specimens containing different amounts of silica fume were maintained in an apparatus in which carbon dioxide pressure and concentration and relative humidity were kept constant, and wetting and drying cycles in saline water were applied. Surface resistivity, sorptivity, CO2 consumption, and carbonation and chloride ion ingress depths measurements were taken. Phase change due to carbonation and chloride ion attack was monitored by XRD analysis, and microstructures and interfacial transition zones were studied by implementing SEM as well as mercury intrusion porosimetry. It was expected to have a synergistic effect in the tidal zone where simultaneous carbonation and chloride ion attack happen. However, the observed reduced surface resistivity, compared to specimens maintained in CO2 gas, could be due to the moisture that is available near the surface, hindering CO2 from penetrating into the pores of the specimens. Moreover, the porosity analysis of the specimens showed that the sample containing silica fume cured in the tidal zone had 50.1% less total porosity than the plain cement paste cured in the same condition.

Air ventilation/controlling facility

Energy Technology Data Exchange (ETDEWEB)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro

1997-12-12

When all electricity supply from the outside of a power plant are lost, a power generator directly connected to an emergency steam turbine which is driven by steams introduced from a nuclear reactor is driven to supply electricity required in the power plant. Cool water prepared by a refrigerator is used as cooling water in an air ventilation/controlling facility of a room equipped with the power generating facility. As the refrigerator, a refrigerator of an existent emergency air cooling water system for an auxiliary air ventilation/controlling equipment is used. This can extend the period of time till the temperature of the room where the power generator is disposed exceeds the temperature range capable of keeping the integrity of the power generator even when all the AC power supply are lost to inactivate the function of the air ventilation/controlling system. (I.S.)

Particulate filtration in nuclear facilities

International Nuclear Information System (INIS)

1991-01-01

The removal of particulate radioactive material from exhaust air or gases is an essential feature of virtually all nuclear facilities. Recent IAEA publications have covered the broad designs of off-gas and air cleaning systems for the range of nuclear power plants and other facilities. This report is a complementary guidebook that examines in detail the latest developments in the design, operation, maintenance and testing of fibrous air filters. The original draft of the report was prepared by three consultants, M.W. First, of the School of Public Health, Harvard University, United States of America, K.S. Robinson, from the UKAEA Harwell Laboratory, United Kingdom, and H.G. Dillmann, of the Kernforschungzentrum, Karlsruhe, Germany. The Technical Committee Meeting (TCM), at which the report was reviewed and much additional information contributed, was attended by 11 experts and was held in Vienna, from 30 May to 3 June 1988. 64 refs, 41 figs, 10 tabs

Nuclear energy in the space: panorama 1985

International Nuclear Information System (INIS)

Corcuera, R.P.

1985-01-01

A panoramic view of different areas where nuclear energy can be applied in space is given. These are: radioisotope thermoelectric generators, nuclear reactors for space stations, space crafts and air crafts. The principal difficulties are pointed out and the safety aspect is emphasized. (author)

Measurement of air dose rates over a wide area around the Fukushima Dai-ichi Nuclear Power Plant through a series of car-borne surveys.

Science.gov (United States)

Andoh, Masaki; Nakahara, Yukio; Tsuda, Shuichi; Yoshida, Tadayoshi; Matsuda, Norihiro; Takahashi, Fumiaki; Mikami, Satoshi; Kinouchi, Nobuyuki; Sato, Tetsuro; Tanigaki, Minoru; Takamiya, Koichi; Sato, Nobuhiro; Okumura, Ryo; Uchihori, Yukio; Saito, Kimiaki

2015-01-01

A series of car-borne surveys using the Kyoto University RAdiation MApping (KURAMA) and KURAMA-II survey systems has been conducted over a wide area in eastern Japan since June 2011 to evaluate the distribution of air dose rates around the Fukushima Dai-ichi Nuclear Power Plant and to evaluate the time-dependent trend of decrease in air dose rates. An automated data processing system for the KURAMA-II system was established, which enabled rapid analysis of large amounts of data obtained using about 100 KURAMA-II units. The initial data used for evaluating the migration status of radioactive cesium were obtained in the first survey, followed by other car-borne surveys conducted over more extensive and wider measurement ranges. By comparing the measured air dose rates obtained in each survey (until December 2012), the decreasing trend of air dose rates measured through car-borne surveys was found to be more pronounced than those expected on the basis of the physical decay of radioactive cesium and of the air dose rates measured using NaI (Tl) survey meters in the areas surrounding the roadways. In addition, it was found that the extent of decrease in air dose rates depended on land use, wherein it decreased faster for land used as building sites than for forested areas. Copyright © 2014 Elsevier Ltd. All rights reserved.

The new context for transport of radioactive nuclear material

International Nuclear Information System (INIS)

Anne, Catherine; Galtier, Jerome

2001-01-01

The transportation of radioactive and nuclear materials, involves all modes of transportation (road, air, sea, rail) with predominance for road and for air (air for radioisotopes). In this paper we examine the impact of new evolutions in the fields of safety, security, logistics means, public acceptance and quality assurance

The nuclear power generation

International Nuclear Information System (INIS)

Serres, R.

1999-01-01

The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants

International Nuclear Information System (INIS)

Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

1995-05-01

Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures

Peculiarities of radionuclide contamination of different Semipalatinsk nuclear test site (SNTS) zones

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Khazhekber, S.; Lukashenko, S.N.; Solodukhin, V.P.; Kazachevskij, I.V.; Poznyak, V.L.; Knyazev, B.B.; Rofer, Ch.

2002-01-01

The Semipalatinsk Nuclear Test Site occupies about 18500 km 2 . There are 3 basic test zones in this territory including various test platforms where different character nuclear explosions were carried out. On the test platforms of the 'Opytnoe Pole' zone air and ground tests were performed, including nuclear and hydronuclear (without nuclear reaction) explosions. On the other zones (the Degelen mountains and Balapan valley) the underground tests including camouflaged and excavation nuclear explosions were carried out. Each kind of these tests can be characterised by the quantity and composition of radionuclides which were formed during the nuclear explosion, by the area of their distribution, localisation of the radionuclides at various sites, radionuclide species in soil. Transfer of the products of the air and the ground nuclear explosions by air flows and their sedimentation on the ground surfaces have caused broadband radioactive plumes extending over hundreds of kilometres. As a result of hydronuclear experiments, plenty of alpha-active radionuclides, consisting of a nuclear device is thrown locally out. Besides the ground and the air explosions, radiation conditions of the territory of the SNTS were influenced by excavation explosions with ground throwing out. Such tests resulted in an intensive local pollution. Other zone of an original pollution is the Degelen mountains. Although an basic mass of the nuclear explosion products is obviously concentrated in basin cavities of the tunnels, the radionuclides are taken out on a day time surface together with waters acting in the basin cavity of the tunnels. The results of investigation of radionuclide pollution on the various platforms of the SNTS territory are presented. The results characterise the radionuclide pollution by specificity of spent tests

Respiratory and protective equipment at a large nuclear facility

International Nuclear Information System (INIS)

Zippler, D.B.

1975-12-01

A variety of personal protective equipment is used in a large nuclear facility to protect employees against both nuclear and ordinary industrial materials. Equipment requirements are based on risk evaluation and may range from a minimum of shoe covers to whole body protection by air-supplied plastic suits. Types of equipment are listed and one-year costs are given. Criteria for evaluating and compartmentalizing risks are discussed. Air-supplied suits and hoods are discussed in detail

Model of tritium transfer into environment by the personnel of nuclear enterprises

International Nuclear Information System (INIS)

Batalin, J.; Krechetova, A.

2004-01-01

One of the ways of radionuclide transfer from a nuclear enterprise into an environment is analysed. This way of transfer is the transport of radionuclides by the personnel of a nuclear enterprise. During an active work in a nuclear enterprise the personnel accumulate radionuclides from the air of industrial premises. Accumulated radionuclides are released from the organism into an environment according to the effective period of half-draw. The main part of radionuclides is transferred from the organism of professional workers into an environment: first of all into the air and on furniture of their dwellings and later - into the organisms of their family members. In this way contamination of workers' dwellings and irradiation of their family members exceed the contamination through air and water. The model is confirmed as an example of tritium transfer from nuclear enterprises. (author)

Children's (Pediatric) Nuclear Medicine

Medline Plus

Full Text Available ... bones. liver and gallbladder. gastrointestinal tract. heart. lungs. brain. thyroid. Nuclear medicine scans are typically used to ... differently than when breathing room air or holding his or her breath. With some exams, a catheter ...

Canyon air flow measurement utilizing ASME standard pitot tube arrays

International Nuclear Information System (INIS)

Moncrief, B.R.

1990-01-01

The Savannah River Site produces nuclear materials for national defense. In addition to nuclear reactors, the site has separation facilities for reprocessing irradiated nuclear fuel. The chemical separation of highly radioactive materials takes place by remote control in large buildings called canyons. Personnel in these buildings are shielded from radiation by thick concrete walls. Contaminated air is exhausted from the canyons and contaminants are removed by sand filters prior to release to the atmosphere through a stack. When these facilities were built on a crash basis in the early 1950's, inadequate means were provided for pressure and air flow measurement. This presentation describes the challenge we faced in retrofitting a highly radioactive, heavily shielded facility with instrumentation to provide this capability

Report of the Secretary of Defense Task Force on DoD Nuclear Weapons Management. Phase II: Review of the DoD Nuclear Mission

National Research Council Canada - National Science Library

Schlesinger, James R; Carns, Michael P; Crouch, II, J. D; Gansler, Jacques S; Giambastiani, Jr., Edmund P; Hamre, John J; Miller, Franklin C; Williams, Christopher A; Blackwell, Jr, James A

2008-01-01

Incidents related to the Air Force's mishandling of nuclear weapons and components led to the creation of the Task Force in June 2008 to provide advice on nuclear matters for the Secretary of Defense...

Nuclear Emergency and the Atmospheric Dispersion of Nuclear Aerosols: Discussion of the Shared Nuclear Future - 13163

International Nuclear Information System (INIS)

Rana, Mukhtar A.; Ali, Nawab; Akhter, Parveen; Khan, E.U.

2013-01-01

This paper has a twofold objective. One is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. Other is to understand the aerosol formation in the atmosphere for the case of the leakage from the nuclear waste containers or a nuclear accident. Radio-nuclides released from the waste will attach themselves to the existing aerosols in the atmosphere along with formation of new aerosols. Anticipating the nuclear accident when a variety of radioactive aerosols will form and exist in the atmosphere, as a simple example, measurement of naturally existing radioactive aerosols are made in the atmosphere of Islamabad and Murree. A comparison with similar measurements in 3 cities of France is provided. Measurement of radionuclides in the atmosphere, their attachment to aerosols and follow up transport mechanisms are key issues in the nuclear safety. It is studied here how "7Be concentration in the atmospheric air varies in the capital city of Islamabad and a Himalaya foothill city of Murree (Pakistan). Present results are compared with recent related published results to produce a "7Be concentration versus altitude plot up to an altitude of 4000 m (a.s.l.). Origin and variance of "7Be concentration at different altitudes is discussed in detail. The relevance of results presented here with the evaluation of implications of Chernobyl and Fukushima nuclear disasters has been discussed in a conclusive manner. It is the first international report of a joint collaboration/project. The project is being generalized to investigate and formulate a smooth waste storage and disposal policy. The project will address the fission and fusion waste reduction, its storage, its recycling, air, water and soil quality

Nuclear Emergency and the Atmospheric Dispersion of Nuclear Aerosols: Discussion of the Shared Nuclear Future - 13163

Energy Technology Data Exchange (ETDEWEB)

Rana, Mukhtar A. [Science-Admin Coherence Cell (SACC), PINSTECH Admin Blk, PAEC, Islamabad (Pakistan); Ali, Nawab [Physics Division, Directorate of Science, Pakistan Institute of Nuclear Science and Technology (PINSTECH), P.O. Nilore, Islamabad (Pakistan); Akhter, Parveen [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad (Pakistan); Khan, E.U. [Department of Physics, International Islamic University (IIU), Kettle Fields, Kashmir Highways, Islamabad (Pakistan)

2013-07-01

This paper has a twofold objective. One is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. Other is to understand the aerosol formation in the atmosphere for the case of the leakage from the nuclear waste containers or a nuclear accident. Radio-nuclides released from the waste will attach themselves to the existing aerosols in the atmosphere along with formation of new aerosols. Anticipating the nuclear accident when a variety of radioactive aerosols will form and exist in the atmosphere, as a simple example, measurement of naturally existing radioactive aerosols are made in the atmosphere of Islamabad and Murree. A comparison with similar measurements in 3 cities of France is provided. Measurement of radionuclides in the atmosphere, their attachment to aerosols and follow up transport mechanisms are key issues in the nuclear safety. It is studied here how {sup 7}Be concentration in the atmospheric air varies in the capital city of Islamabad and a Himalaya foothill city of Murree (Pakistan). Present results are compared with recent related published results to produce a {sup 7}Be concentration versus altitude plot up to an altitude of 4000 m (a.s.l.). Origin and variance of {sup 7}Be concentration at different altitudes is discussed in detail. The relevance of results presented here with the evaluation of implications of Chernobyl and Fukushima nuclear disasters has been discussed in a conclusive manner. It is the first international report of a joint collaboration/project. The project is being generalized to investigate and formulate a smooth waste storage and disposal policy. The project will address the fission and fusion waste reduction, its storage, its recycling, air, water and soil

Device for separating, purifying and recovering nuclear fuel material, impurities and materials from impurity-containing nuclear fuel materials or nuclear fuel containing material

International Nuclear Information System (INIS)

Sato, Ryuichi; Kamei, Yoshinobu; Watanabe, Tsuneo; Tanaka, Shigeru.

1988-01-01

Purpose: To separate, purify and recover nuclear fuel materials, impurities and materials with no formation of liquid wastes. Constitution: Oxidizing atmosphere gases are introduced from both ends of a heating furnace. Vessels containing impurity-containing nuclear fuel substances or nuclear fuel substance-containing material are continuously disposed movably from one end to the other of the heating furnace. Then, impurity oxides or material oxides selectively evaporated from the impurity-containing nuclear fuel substances or nuclear fuel substance-containing materials are entrained in the oxidizing atmosphere gas and the gases are led out externally from a discharge port opened at the intermediate portion of the heating furnace, filters are disposed to the exit to solidify and capture the nuclear fuel substances and traps are disposed behind the filters to solidify and capture the oxides by spontaneous air cooling or water cooling. (Sekiya, K.)

Nuclear materials transportation

International Nuclear Information System (INIS)

Ushakov, B.A.

1986-01-01

Various methods of nuclear materials transportation at different stages of the fuel cycle (U 3 O 8 , UF 6 production enrichment, fuel element manufacturing, storage) are considered. The advantages and drawbacks of railway, automobile, maritime and air transport are analyzed. Some types of containers are characterized

17th DOE nuclear air cleaning conference: proceedings. Volume 2

International Nuclear Information System (INIS)

First, M.W.

1983-02-01

Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier

17th DOE nuclear air cleaning conference: proceedings. Volume 2

Energy Technology Data Exchange (ETDEWEB)

First, M.W. (ed.)

1983-02-01

Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier.

Environmental radioactivity levels, Browns Ferry Nuclear Plant: Annual report, 1986

International Nuclear Information System (INIS)

1986-04-01

The report presents data gathered during radiological monitoring program conducted in the environs of the Browns Ferry Nuclear Plant. Dose estimates were made from concentrations of radioactivity found in samples of media including air, milk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 95% of those doses were contributed by the naturally occurring K-40 and by Sr-90 and Cs-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing. Increased levels of I-131 were reported in air, milk, and rainwater following the accident at the Chernobyl nuclear power station. In addition, Ru-103, Cs-137, and Cs-134 were identified in air particulates, and traces of Ru-103 were found in rainwater

Nuclear power and public health in Michigan, July 1974-June 1976

International Nuclear Information System (INIS)

Anon.

1978-01-01

Environmental samples in the form of air particulates, air vapors, precipitation, external radiation, milk, drinking water, surface water, and aquatic biota were taken from various sites in Michigan and analyzed to determine if any effects due to nuclear power reactors could be detected. Seasonal and geographical variations in the air particulate gross beta data are evident and are attributable to corresponding variations in fallout from nuclear tests. No gross beta, gross alpha, or gross gamma results of air particulate and air vapor samples were found to be indicative of reaction operations. Precipitation data displayed similar trends, following the fallout cycle, while specific elevated results are attributable to sample size and not reactor operations. All milk results have been found to be well within the appropriate maximum permissible concentrations for the general population. In no cases did the data indicate either specific atmospheric nuclear tests or reactor operations. All drinking water results were so close to their respective minimum sensitivities that no specific or general trends due to nuclear power plant operations were indicated. No results exceeded either existing Public Health Service limits or the new EPA drinking water standards. While no general trends attributable to reactor operations were found in surface water results, specific plant liquid releases were revealed by the network. All detected radioactivity was below appropriate limits. Although barely detectable amounts of radioactivity were found in aquatic biota samples, no results were determined to be indicative of specific nuclear plant discharges. The cumulative results indicate that no public health problem exists

History of the Iraqi Nuclear Center of Tuwaitha

International Nuclear Information System (INIS)

Fabbri, Silvio

2009-01-01

The Tuwaitha site, 20 km south of Baghdad, was chosen at the beginning of the sixties to be the Center for Research and Development of the Iraqi Nuclear Program. The israeli air attack to the Osirak reactor in 1981, the clandestine activities for nuclear weapons production and the inspections carried out by the International Atomic Energy Agency (IAEA) to verify such activities are parts of the history of that nuclear complex. Its installations were extensively damaged in 1991 during the so called Golf War and finally destroyed by air bombardment during the invasion by the Coalition Forces in 2003. The IAEA and other several countries have elaborated an international assistance program for the future activities of installations dismantling and site remediation. (author) [es

Proceedings of NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education

International Nuclear Information System (INIS)

Constantin, Marin; Turcu, Ilie

2008-01-01

The proceedings of the NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 28 - 30 2008 contain 88 communications presented in 3 sections addressing the themes of Nuclear energy, Environmental protection, and Sustainable development. In turn these sections are addressing the following items: Section 1.1 - Nuclear safety and severe accidents (12 papers); Section 1.2 - Nuclear reactors (11 papers); Section 1.3 - Nuclear technologies and materials (20 papers); Section 2.1 - Radioprotection (5 papers); Section 2.2 - Radioactive waste management (20 papers); Section 2.3 - air, water and soil protection (5 papers); Section 3.1 - Strategies in energy (3 papers); Section 3.2 - Education, continuous formation and knowledge transfer (8 papers); Section 3.3 - International partnership for a sustainable development (4 papers)

Experimental verification of air flow rate measurement for representative isokinetic air sampling in ventilation stacks

International Nuclear Information System (INIS)

Okruhlica, P.; Mrtvy, M.; Kopecky, Z.

2009-01-01

Nuclear facilities are obliged to monitor their discharge's influence on environment. Main monitored factions in NPP's ventilation stacks are usually noble gasses, particulates and iodine. These factions are monitored in air sampled from ventilation stack by means of sampling rosette and bypass followed with on-line measuring monitors and balance sampling devices with laboratory evaluations. Correct air flow rate measurement and representative iso-kinetic air sampling system is essential for physical correct and metrological accurate evaluation of discharge influence on environment. Pairs of measuring sensors (Anemometer, pressure gauge, thermometer and humidity meter) are symmetrically placed in horizontal projection of stack on positions based on measured air flow velocity distribution characteristic, Analogically diameter of sampling rosette nozzles and their placement in the middle of 6 - 7 annuluses are calculated for assurance of representative iso-kinetic sampling. (authors)

Experimental verification of air flow rate measurement for representative isokinetic air sampling in ventilation stacks

International Nuclear Information System (INIS)

Okruhlica, P.; Mrtvy, M.; Kopecky, Z.

2008-01-01

Nuclear facilities are obliged to monitor their discharge's influence on environment. Main monitored factions in NPP's ventilation stacks are usually noble gasses, particulates and iodine. These factions are monitored in air sampled from ventilation stack by means of sampling rosette and bypass followed with on-line measuring monitors and balance sampling devices with laboratory evaluations. Correct air flow rate measurement and representative iso-kinetic air sampling system is essential for physical correct and metrological accurate evaluation of discharge influence on environment. Pairs of measuring sensors (Anemometer, pressure gauge, thermometer and humidity meter) are symmetrically placed in horizontal projection of stack on positions based on measured air flow velocity distribution characteristic, Analogically diameter of sampling rosette nozzles and their placement in the middle of 6- 7 annuluses are calculated for assurance of representative iso-kinetic sampling. (authors)

Process for contamination containment of a workplace by means of an air jet

International Nuclear Information System (INIS)

Meline, F.

1984-01-01

Containment of pollution in an area, for example the room where nuclear fuel elements are cut, is obtained by an air curtain directed by a second air jet to improve the containment of pollutants. Contamined air is extracted by a cyclone and filtered [fr

New developments in the air transport of plutonium

International Nuclear Information System (INIS)

Andersen, J.A.

1978-01-01

A new package for the air transport of plutonium has been developed in response to a United States Public Law which restricts the US air transport of plutonium except for small medical devices. This new package, called PAT-1 for plutonium air transportable package model 1, is the result of the NRC-sponsored PARC (plutonium accident resistant container) project at Sandia Laboratories, Albuquerque. The PAT-1 package is designed to meet or exceed new criteria specified in NUREG-0360. These include a severe test sequence of impact (greater than 250 KTS) on an unyielding target, crush, puncture, slash, a large JP-4 fire for 1 hour, followed by water immersion, with stringent acceptance standards on plutonium release, nuclear shielding, and nuclear criticality. The PAT-1 package design features a high energy absorption capability with high-level fire protection. It weighs approximately 227 kg (500 lb) when loaded with 2 kg PuO 2 , and can accommodate up to 25 watts thermal energy from the plutonium load

Course on internal dosimetry in nuclear medicine; Curso de dosimetria interna en medicina nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This documentation was distributed to the participants in the Course of Internal Dosimetry in Nuclear Medicine organised by the Nuclear Regulatory Authority (ARN) of Argentina and held in Buenos Aires, Argentina, August 9-13, 2004. The course was intended for people from IAEA Member States in the Latin American and Caribbean region, and for professionals and workers in medicine, related with the radiation protection. Spanish and English were the languages of the course. The following subjects were covered: radioprotection of the patient in nuclear medicine; injuries by ionizing radiations; MIRD methodology; radiation dose assessment in nuclear medicine; small scale and microdosimetry; bone and marrow dose modelling; medical internal dose calculations; SPECT and image reconstruction; principles of the gamma camera; scattering and attenuation correction in SPECT; tomography in nuclear medicine.

Countering Putin’s Nuclear Backed Aggression with a Continuous Nuclear Capable Bomber Presence

Science.gov (United States)

2016-05-13

bribery and propaganda to instigate protesting within the populace and thus destabilize Ukraine. 16 Russia was very careful to legally qualify any...proved again that Putin is willing to use different tactics to secure their buffer zone. Though the aggression into the Ukraine was called “an act of...Credible Nuclear Deterrent.” Air and Space Journal. (Fall, 2010 ). 29 Pifer, Steven. “Obama’s Faltering Nuclear Legacy: The 3 Rs.” The Washington

Nuclear energy

International Nuclear Information System (INIS)

Lotter, A.C.

1979-01-01

The recent, terrifying threat of a major calamity at Pennsylvania's Three Mile Island power plant near Harrisburg reverberated across practically the whole of the civilised world. An almost incredible sequence of human and mechanical failures at this installation had stopped just short of disaster and had brought the unthinkable perilously close to happening. The accident had sprayed radioactive waste into the air and had led to the large scale evacuation of people from the endangered area, disrupted hundreds of thousands of lives and caused a crippling setback to the nuclear industry. In this article the author discusses the impact the Harrisburg incident has had on the nuclear industry

Shocks from high-energy nuclear-interacting particles in the mountain Chakaltajya

Energy Technology Data Exchange (ETDEWEB)

Kamata, K [Tokyo Univ. (Japan)

1975-06-01

Experimental investigations of extensive air showers at the height of 5200 m above the sea level have been performed. The behaviour of high energy nuclear active particles in the cores of the showers has been studied using the nuclear knock-on method. The cross section of the proton inelastic interaction with the air is shown to increase with energy in the energy range of 3-9 TeV.

USNRC regulatory guidance for engineered safety feature air cleaning systems

International Nuclear Information System (INIS)

Bellamy, R.R.

1991-01-01

The need for clear, technically appropriate, and easily implementable guidance for the design, testing, and maintenance of nuclear air cleaning systems has long been recognized. Numerous industry consensus standards have been issued and revised over the last 30 years. Guidance has also been published by the US Nuclear Regulatory Commission in the form of regulations, regulatory guides, standard review plans, NUREG documents, and information notices. This paper will summarize the latest revisions to these documents and emphasize Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for Post-Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, which was last revised in 1978. The USNRC has undertaken a project to revise this regulatory guide, and the status of that revision is highlighted

Proceedings of NUCLEAR 2009 international conference on sustainable development through nuclear research and education

International Nuclear Information System (INIS)

Constantin, Marin; Turcu, Ilie

2009-01-01

The proceedings of the NUCLEAR 2009 international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 27 - 29 2009 contain 92 communications presented in two plenary sessions (6 and 4 talks, respectively) and three sections addressing the themes of Nuclear energy, Environmental protection, and Sustainable development. In turn these sections are addressing the following items: Section 1.1 - Nuclear safety and severe accidents (8 papers); Section 1.2 - Nuclear reactors (15 papers); Section 1.3 - Nuclear technologies and materials (32 papers); Section 2.1 - Radioactive waste management (18 papers; Section 2.2 and Section 2.3 - Radioprotection and air, water and soil protection (12 papers); Section 3.1 - Education, continuous formation and knowledge transfer (9 papers); Section 3.2 -Strategies in energy (Round table) (5 papers). A number of 17 papers although programmed have not actually been presented within these proceedings. These papers are presented as abstracts in 'Nuclear 2009 - BOOK of ABSTRACTS', separately processed

Are we Breathing Clean Air in Metro Manila? (Nuclear and Related Analytical Techniques and Receptor Modeling Revealing the Real Score)

International Nuclear Information System (INIS)

Pabroa, Preciosa Corazon B.

2015-01-01

Air Particulate matter (APM) is a mixture of different pollutant sources which can be of anthropogenic and/or natural origin, of which the size of great concern with regard to adverse effects on human health are generally less than 10μm (Referred to as PM10). Identification and apportionment of pollutant sources is important to be able to have better understanding of prevailing conditions in the area and thus better air quality management can be applied. APM (PM10) at sampling sites in Metro Manila (Philippines) has been monitored since 1998 for the primary purpose of source identification and source apportionment. APM samples (fractionated into coarse (PM2.5-10) and fine (PM2.5) fractions) were collected using a Gent air sampler. Particulate mass was determined by gravimetry and black carbon by reflectometry organic carbon/elemental carbon by thermal optical reflectance. Elemental concentrations were determined using nuclear and related analytical techniques such as the particle-induced x-ray emission (PIXE) spectrometry and x-ray fluorescence (XRF) spectrometry. Source apportionment of fine air particles was done using PMF2. Result show PM10 levels to be in compliance to the Philippine 1-year guideline value of 60 μg m“-“3 but in exceedance of the US EPA 1-year standard of 15 μg m“-“3 and the WHO 1-year guideline value of 10 μg m“-“3. Annual mean % Fine BC levels range from 33% to 59%, but individual points can reach up to more than 80% of the PM2.5 levels. Pb level in the fine fraction exhibit decreasing trend coinciding with the introduction of unleaded-gasoline starting in 1998 and the eventual phase-out of the use of leaded-gasoline in 2001. Six air pollution sources have been identified in the fine fraction with vehicular emissions making up the bulk at about 50%. Other sources are smoke, secondary S, fine soil and industry. Addressing problems regarding traffic-related activities can greatly reduce the fine particulate pollution problems

Surface area-burnoff correlation for the steam--graphite reaction

International Nuclear Information System (INIS)