Toxic Release Inventory (TRI) Facility Points, Region 9, 2014, US EPA Region 9

Data.gov (United States)

U.S. Environmental Protection Agency — A federal law called the Emergency Planning and Community Right to Know Act (EPCRA) gives the public the right to know about toxic chemicals being released into the...

Toxic Release Inventory (TRI) Facility Points, Region 9, 2011, US EPA Region 9

Data.gov (United States)

U.S. Environmental Protection Agency — A federal law called the Emergency Planning and Community Right to Know Act (EPCRA) gives the public the right to know about toxic chemicals being released into the...

RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release

International Nuclear Information System (INIS)

Wenzel, Douglas R.; Schrader, Brad J.

2007-01-01

1 - Description of program or function: RSAC-6 is the latest version of the program RSAC (Radiological Safety Analysis Computer Program). It calculates the consequences of a release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory; decay and in-grow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Internal dose from the inhalation and ingestion pathways is calculated. External dose from ground surface and plume gamma pathways is calculated. New and exciting updates to the program include the ability to evaluate a release to an enclosed room, resuspension of deposited activity and evaluation of a release up to 1 meter from the release point. Enhanced tools are included for dry deposition, building wake, occupancy factors, respirable fraction, AMAD adjustment, updated and enhanced radionuclide inventory and inclusion of the dose-conversion factors from FOR 11 and 12. 2 - Methods: RSAC6 calculates meteorological dispersion in the atmosphere using Gaussian plume diffusion for Pasquill-Gifford, Hilmeier-Gifford and Markee models. A unique capability is the ability to model Class F fumigation conditions, the meteorological condition that causes the highest ground level concentrations from an elevated release. Doses may be calculated for various pathways including inhalation, ingestion, ground surface, air immersion, water immersion pathways. Dose calculations may be made for either acute or chronic releases. Internal doses (inhalation and ingestion) are calculated using the ICRP-30 model with dose conversion factors from FOR 11. External factors are calculated using FOR 12. 3 - Unusual Features: RSAC6 calculates complete progeny in-growth and decay during all accident phases. The calculation of fission product inventories in particularly useful in the analysis of accidents where the

The inventory of sources, environmental releases and risk assessment for perfluorooctane sulfonate in China

International Nuclear Information System (INIS)

Zhang Lai; Liu Jianguo; Hu Jianxin; Liu Chao; Guo Weiguang; Wang Qiang; Wang Hong

2012-01-01

With about 100 t/y of the production volume, perfluorootane sulfonates (PFOS) are mainly used for metal plating, aqueous fire-fighting foams (AFFFs) and sulfluramidin China, and the use amount is about 30–40 t/y, 25–35 t/y and 4–8 t/y respectively. Based on the inventory of PFOS production and uses with geographic distribution educed from statistics, environmental risk assessment of PFOS was taken by using EUSES model, as well as its environmental releases were estimated both in local and regional levels in China. While the environmental release from manufacture is significant in Central China region, metal plating was identified as the major PFOS release source in regional level. The East China region shows the most strong emission strength of PFOS. Though the predicted environmental concentrations (PECs) were not exceed current relevant predicted no effect concentrations (PNECs) of the risk characterization for PFOS, higher PECs was estimated around major PFOS release sources showing undesirable environmental risk at local level. - Highlights: ► Inventory of production and uses of perfluorooctane sulfonate (PFOS) in China with geographical distribution. ► Characteristics of PFOS release sources and distribution consistent with social-economic situation in China. ► Effective model predicted results of PFOS environmental risk assessment in local and regional scales compared with relevant environmental monitoring data. - Inventory of PFOS production and use of with sectoral and regional distribution of China, environmental releases and risk status were indicated both in the local and regional level of the country.

2001 Toxic Chemical Release Inventory Emergency Planning and Community Right to Know Act SEC 313

International Nuclear Information System (INIS)

ZALOUDEK, D.E.

2002-01-01

Pursuant to section 313 of the Emergency Planning and Community Right-To-Know Act of 1986 (EPCRA), and Executive Order 13148, Greening the Government Through Leadership in Environmental Management, the US Department of Energy has prepared and submitted a Toxic Chemical Release Inventory for the Hanford Site covering activities performed during calendar year 2001. EPCRA Section 313 requires facilities that manufacture, process, or otherwise use listed toxic chemicals in quantities exceeding established threshold levels to report total annual releases of those chemicals. During calendar year 2001, Hanford Site activities resulted in one chemical used in amounts exceeding an activity threshold. Accordingly, the Hanford Site 2001 Toxic Chemical Release Inventory, DOE/RL-2002-37, includes total annual amount of lead released to the environment, transferred to offsite locations, and otherwise managed as waste

Toxic Releases/IGD: EF_TRI

Data.gov (United States)

U.S. Environmental Protection Agency — EF_TRI is a subset of facilities from FRS_INTEREST and FRS_FACILITY_SITE which are updated on a monthly basis as part of the Locational Reference Tables (LRT)...

An assessment of the tritium inventory in, permeation through and releases from the NET plasma facing materials

International Nuclear Information System (INIS)

Wu, C.H.

1986-01-01

The tritium retention, permeation and release characteristics of D-T tokamaks are extremely important from both an environmental and a plasma physics point of view. Tokamak measurements have demonstrated that release of retained hydrogen isotopes by plasma-wall interactions play a dominant role in fuel recycling during a discharge. In addition, retained tritium in the plasma facing materials may contribute substantially to the on-site tritium inventory of D-T devices. Austenitic and martensitic steels are being considered as first wall materials. Tungsten and molybdenum will be possibly used as divertor armour materials for NET. By using a computer code, the tritium inventory in, permeation through and release from these materials have been calculated as functions of material thickness, temperature and impinging fluxes. It is shown that the tritium inventory in the first wall will be strongly affected by the temperature gradient in the materials. It is evident, that the tritium permeation as well as the tritium inventory can be reduced appropriately by controlling the temperatures at the plasma and cooling sides of the first wall. The results are discussed and the possible consequences are analysed. (author)

2008 Toxic Chemical Release Inventory 2008 Toxic Chemical Release Inventory Community Right-to-Know Act of 1986, Title III, Section 313

Energy Technology Data Exchange (ETDEWEB)

Ecology and Air Quality Group

2009-10-01

For reporting year 2008, Los Alamos National Laboratory (LANL) submitted a Form R report for lead as required under the Emergency Planning and Community Right-to- Know Act (EPCRA) Section 313. No other EPCRA Section 313 chemicals were used in 2008 above the reportable thresholds. This document was prepared to provide a description of the evaluation of EPCRA Section 313 chemical use and threshold determinations for LANL for calendar year 2008, as well as to provide background information about data included on the Form R reports. Section 313 of EPCRA specifically requires facilities to submit a Toxic Chemical Release Inventory Report (Form R) to the U.S. Environmental Protection Agency (EPA) and state agencies if the owners and operators manufacture, process, or otherwise use any of the listed toxic chemicals above listed threshold quantities. EPA compiles this data in the Toxic Release Inventory database. Form R reports for each chemical over threshold quantities must be submitted on or before July 1 each year and must cover activities that occurred at the facility during the previous year. In 1999, EPA promulgated a final rule on persistent bioaccumulative toxics (PBTs). This rule added several chemicals to the EPCRA Section 313 list of toxic chemicals and established lower reporting thresholds for these and other PBT chemicals that were already reportable. These lower thresholds became applicable in reporting year 2000. In 2001, EPA expanded the PBT rule to include a lower reporting threshold for lead and lead compounds. Facilities that manufacture, process, or otherwise use more than 100 lb of lead or lead compounds must submit a Form R.

76 FR 60781 - Toxics Release Inventory (TRI) Reporting for Facilities Located in Indian Country and...

Science.gov (United States)

2011-09-30

... increase awareness of toxic releases within Tribal communities, thereby increasing the understanding of potential human health and ecological impacts from these hazardous chemicals. DATES: Comments must be... 212221, 212222, 212231, 212234, 212299 (correspond to SIC 10, Metal Mining (except 1011, 1081, and 1094...

Comparing rankings of selected TRI organic chemicals for two environments using a level III fugacity model and toxicity

International Nuclear Information System (INIS)

Edwards, F.G.; Egemen, E.; Nirmalakhandan, N.

1998-01-01

The Toxics Release Inventory, TRI (USEPA, 1995) is a comprehensive listing of chemicals, mass released, source of releases, and other related information for chemicals which are released into the environment in the US. These chemicals are then ranked according to the mass released as a indication of their environmental impact. Industries have been encouraged to adopt production methods to decrease the release of chemicals which are ranked highly in the TRI. Clearly, this ranking of the chemicals based upon the mass released fails to take into account very important environmental aspects. The first and most obvious aspect is the wide range of toxicity's of the chemicals released. Numerous researchers have proposed systems to rank chemicals according to their toxicity. The second aspect, which a mass released based ranking does not take into account, is the fate and transport of each chemical within the environment. Cohen and Ryan (1985) and Mackay and Paterson (1991) have proposed models to evaluate the fate and transport of chemicals released into the environment. Some authors have incorporated the mass released and toxicity with some fate and transport aspects to rank the impact of released chemicals. But, due to the complexities of modeling the environment, the lack of published data on properties of chemicals, and the lack of information on the speciation of chemicals in complex systems, modeling the fate and transport of toxic chemicals in the environment remains difficult. To provide an indication of the need to rank chemicals according to their environmental impact instead of the mass released, the authors have utilized a subset of 45 organic chemicals from the TRI, modeled the fate and transport of the chemicals using a Level III fugacity model, and compared those equilibrium concentrations with toxicity data to yield a hazard value for each chemical

Environmental Carcinogen Releases and Lung Cancer Mortality in Rural-Urban Areas of the United States

Science.gov (United States)

Luo, Juhua; Hendryx, Michael

2011-01-01

Purpose: Environmental hazards are unevenly distributed across communities and populations; however, little is known about the distribution of environmental carcinogenic pollutants and lung cancer risk across populations defined by race, sex, and rural-urban setting. Methods: We used the Toxics Release Inventory (TRI) database to conduct an…

Calculation of tritium inventory and permeation in an INTOR like tokamak device and of its release after shut down

International Nuclear Information System (INIS)

Wienhold, P.; Waelbroeck, F.s; Winter, J.; Ali-Khan, I.

1980-12-01

The tritium inventory in the wall, its escape via permeation and its release in general are evaluated during the operation and later shut-down phases of a tokamak like INTOR by means of the PERI code. No real tritium problem arises after shut-down: simple outgasing techniques at wall temperatures Tsub(W) of approx. 500 0 C should decrease the tritium release rate down to a sufficient low level. Very serious problems are on the other hand expected to arise in the areas of inventory and permeation of tritium during the operation phase: one has the choice between e.g. operating at Tsub(W) = 350 0 C with a quasi-stationary tritium inventory of some 100 grams and a permeation flux phisub(p) approx. 1 gram/day or increasing Tsub(W) to 500 0 C, reducing the inventory down to some grams, but have then a leakage rate by permeation of 35 grams/day. For Tsub(W) = 100 0 C the tritium release into the torus will be intolerable. These figures are confirmed by preliminary measurements on Inconel 600. A suggestion is made as to how to alleviate the problem. (orig.) [de

75 FR 65705 - Notice of Intent To Rule on Request To Release Airport Property at the Tri-Cities Regional...

Science.gov (United States)

2010-10-26

... To Release Airport Property at the Tri-Cities Regional Airport, Blountville, TN. AGENCY: Federal... of Blountville, Tennessee. This property, approximately 2.413 acres in Tract 45 and .0324 acres in... 125 of the Wendell H. Ford Aviation [[Page 65706

Inventory of LCIA selection methods for assessing toxic releases. Methods and typology report part B

DEFF Research Database (Denmark)

Larsen, Henrik Fred; Birkved, Morten; Hauschild, Michael Zwicky

method(s) in Work package 8 (WP8) of the OMNIITOX project. The selection methods and the other CRS methods are described in detail, a set of evaluation criteria are developed and the methods are evaluated against these criteria. This report (Deliverable 11B (D11B)) gives the results from task 7.1d, 7.1e......This report describes an inventory of Life Cycle Impact Assessment (LCIA) selection methods for assessing toxic releases. It consists of an inventory of current selection methods and other Chemical Ranking and Scoring (CRS) methods assessed to be relevant for the development of (a) new selection...... and 7.1f of WP 7 for selection methods. The other part of D11 (D11A) is reported in another report and deals with characterisation methods. A selection method is a method for prioritising chemical emissions to be included in an LCIA characterisation of toxic releases, i.e. calculating indicator scores...

RSAC, Gamma Doses, Inhalation and Ingestion Doses, Fission Products Inventory after Fission Products Release

International Nuclear Information System (INIS)

Richardson, L.C.

1967-01-01

1 - Description of problem or function: RSAC generates a fission product inventory from a given set of reactor operating conditions and then computes the external gamma dose, the deposition gamma dose, and the inhalation-ingestion dose to critical body organs as a result of exposure to these fission products. Program output includes reactor operating history, fission product inventory, dosages, and ingestion parameters. 2 - Method of solution: The fission product inventory generated by the reactor operating conditions and the inventory remaining at various times after release are computed using the equations of W. Rubinson in Journal of Chemical Physics, Vol. 17, pages 542-547, June 1949. The external gamma dose and the deposition gamma dose are calculated by determining disintegration rates as a function of space and time, then integrating using Hermite's numerical techniques for the spatial dependence. The inhalation-ingestion dose is determined by the type and quantity of activity inhaled and the biological rate of decay following inhalation. These quantities are integrated with respect to time to obtain the dosage. The ingestion dose is related to the inhalation dose by an input constant

The Impact of Pollution Prevention on Toxic Environmental Releases from U.S. Manufacturing Facilities.

Science.gov (United States)

Ranson, Matthew; Cox, Brendan; Keenan, Cheryl; Teitelbaum, Daniel

2015-11-03

Between 1991 and 2012, the facilities that reported to the U.S. Environmental Protection Agency's Toxic Release Inventory (TRI) Program conducted 370,000 source reduction projects. We use this data set to conduct the first quasi-experimental retrospective evaluation of how implementing a source reduction (pollution prevention) project affects the quantity of toxic chemicals released to the environment by an average industrial facility. We use a differences-in-differences methodology, which measures how implementing a source reduction project affects a facility's releases of targeted chemicals, relative to releases of (a) other untargeted chemicals from the same facility, or (b) the same chemical from other facilities in the same industry. We find that the average source reduction project causes a 9-16% decrease in releases of targeted chemicals in the year of implementation. Source reduction techniques vary in effectiveness: for example, raw material modification causes a large decrease in releases, while inventory control has no detectable effect. Our analysis suggests that in aggregate, the source reduction projects carried out in the U.S. since 1991 have prevented between 5 and 14 billion pounds of toxic releases.

1997 toxic chemical release inventory. Emergency Planning and Community Right-To-Know Act, Section 313

International Nuclear Information System (INIS)

Zaloudek, D.E.

1998-01-01

Two listed toxic chemicals were used at the Hanford Site above established activity thresholds: phosphoric acid and chlorine. Because total combined quantities of chlorine released, disposed, treated, recovered through recycle operations, co-combusted for energy recovery, and transferred to off-site locations for the purpose of recycle, energy recovery, treatment, and/or disposal, amounted to less than 500 pounds, the Hanford Site qualified for the alternate one million pound threshold for chlorine. Accordingly, this Toxic Chemical Release Inventory includes a Form A for chlorine, and a Form B for phosphoric acid

Assessing Canadian inventories to understand the environmental impacts of mercury releases to the Great Lakes region

International Nuclear Information System (INIS)

Trip, Luke; Bender, Tonya; Niemi, David

2004-01-01

North American pollutant release and transfer registries have been continuously developing with an eye to understanding source/receptor relationships and ensuring that the polluter-paid principle is applied to the appropriate parties. The potential contribution of mercury to the Great Lakes Basin arising from the rerelease of historic mercury pollution from contaminated aquatic and terrestrial media is poorly understood and the subject of concern. Although a considerable amount of data may be available on the atmospheric component of mercury releases to the Basin, further inventory work is needed to quantify the rerelease of the historic mercury. Much of the related existing inventory information is either not derived from direct measurement or not bounded by a mass-balance accounting. Critical to this determination is an increased confidence in the inventories of mercury from past and current practices. This may be enhanced through comprehensive and thorough surveys of contributions from specific products and their life-cycle assessments. An even greater challenge is to determine the bioavailability of the mercury emanating from land-based sources and from aquatic media. This paper describes the interplay among the sources and receptors of mercury and provides a quantitative assessment of current Canadian contributions of mercury as a contaminant to the Great Lakes. Recommendations for improved assessments are provided

Petroleum and hazardous material releases from industrial facilities associated with Hurricane Katrina.

Science.gov (United States)

Santella, Nicholas; Steinberg, Laura J; Sengul, Hatice

2010-04-01

Hurricane Katrina struck an area dense with industry, causing numerous releases of petroleum and hazardous materials. This study integrates information from a number of sources to describe the frequency, causes, and effects of these releases in order to inform analysis of risk from future hurricanes. Over 200 onshore releases of hazardous chemicals, petroleum, or natural gas were reported. Storm surge was responsible for the majority of petroleum releases and failure of storage tanks was the most common mechanism of release. Of the smaller number of hazardous chemical releases reported, many were associated with flaring from plant startup, shutdown, or process upset. In areas impacted by storm surge, 10% of the facilities within the Risk Management Plan (RMP) and Toxic Release Inventory (TRI) databases and 28% of SIC 1311 facilities experienced accidental releases. In areas subject only to hurricane strength winds, a lower fraction (1% of RMP and TRI and 10% of SIC 1311 facilities) experienced a release while 1% of all facility types reported a release in areas that experienced tropical storm strength winds. Of industrial facilities surveyed, more experienced indirect disruptions such as displacement of workers, loss of electricity and communication systems, and difficulty acquiring supplies and contractors for operations or reconstruction (55%), than experienced releases. To reduce the risk of hazardous material releases and speed the return to normal operations under these difficult conditions, greater attention should be devoted to risk-based facility design and improved prevention and response planning.

Executive Order 12898 and Social, Economic, and Sociopolitical Factors Influencing Toxic Release Inventory Facility Location in EPA Region 6: A Multi-Scale Spatial Assessment of Environmental Justice

Science.gov (United States)

Moore, Andrea Lisa

2013-01-01

Toxic Release Inventory facilities are among the many environmental hazards shown to create environmental inequities in the United States. This project examined four factors associated with Toxic Release Inventory, specifically, manufacturing facility location at multiple spatial scales using spatial analysis techniques (i.e., O-ring statistic and…

1992 Toxic Chemical Release Inventory: Emergency Planning and Community Right-To-Know-Act of 1986 Section 313

International Nuclear Information System (INIS)

1993-07-01

Section 313 of the Emergency Planning and Community Right-To-Know Act of 1986 (EPCRA) requires the annual submittal of toxic chemical release information to the US Environmental Protection Agency (EPA). The following document is the July 1993 submittal of the EPCRA Toxic Chemical Release Inventory Report (Form R). Included is a Form R for chlorine and for lead, the two chemicals used in excess of the established regulatory thresholds at the Hanford Site by the US Department of Energy, Richland Operations Office and its contractors during calendar year 1992

1998 Toxic Chemical Release Inventory Report for the Emergency Planning and Community Right-to-Know Act of 1986, Title III

International Nuclear Information System (INIS)

Stockton, Marjorie B.

1999-01-01

The Emergency Planning and Community Right-to-Know Act (EPCRA) of 1986 [also known as the Superfund Amendment and Reauthorization Act (SARA), Title III], as modified by Executive Order 12856, requires that all federal facilities evaluate the need to submit an annual Toxic Chemical Release Inventory report as prescribed in Title III, Section 313 of this Act. This annual report is due every July for the preceding calendar year. Owners and operators who manufacture, process, or otherwise use certain toxic chemicals above listed threshold quantities are required to report their toxic chemical releases to all environmental mediums (air, water, soil, etc.). At Los Alamos National Laboratory (LANL), no EPCRA Section 313 chemicals were used in 1998 above the reportable threshold limits of 10,000 lb or 25,000 lb. Therefore LANL was not required to submit any Toxic Chemical Release Inventory reports (Form Rs) for 1998. This document was prepared to provide a detailed description of the evaluation on chemical usage and EPCRA Section 313 threshold determinations for LANL for 1998

An Evaluation of a Fission Product Inventory for CANDU Fuels

International Nuclear Information System (INIS)

Jung, Jong Yeob; Park, Joo Hwan

2007-01-01

Fission products are released by two processes when a single channel accident occurs. One is a 'prompt release' and the other is a 'delayed release'. Prompt release assumes that the gap inventory of the fuel elements is released by a fuel element failure at the time of an accident. Delayed release assumes that the inventories within the grain or at the grain boundary are released after a accident due to a diffusion through grains, an oxidation of the fuel and an interaction between the fuel and the Zircaloy sheath. Therefore, the calculation of a fission product inventory and its distribution in a fuel during a normal operating is the starting point for the assessment of a fission product release for single channel accidents. In this report, the fission product inventories and their distributions within s fuel under a normal operating condition are evaluated for three types of CANDU fuels such as the 37 element fuel, CANFLEX-NU and CANFLEX-RU fuel bundles in the 'limiting channel'. To accomplish the above mentioned purposes, the basic power histories for each type of CANDU fuel were produced and the fission product inventories were calculated by using the ELESTRES code

1995 Toxic chemical release inventory: Emergency Planning and Community Right-to-Know Act of 1986, Section 313

International Nuclear Information System (INIS)

Mincey, S.L.

1996-08-01

Section 313 of the Emergency Planning and Community Right-To-Know Act (EPCRA) requires the annual submittal of toxic chemical release information to the U.S. Environmental Protection Agency.Executive Order 12856, 'Federal Compliance With Right-to-Know Laws and Pollution Prevention Requirements' extends the requirements of EPCRA to all Federal agencies. The following document is the August 1996 submittal of the Hanford Site Toxic Chemical Release Inventory report. Included is a Form R for ethylene glycol, the sole chemical used in excess of the established regulatory thresholds at the Hanford Site by the U.S. Department of Energy, Richland Operations Office and its contractors during Calendar Year 1995

7 CFR 930.57 - Secondary inventory reserve.

Science.gov (United States)

2010-01-01

... shall retain control over the release of any cherries from the secondary inventory reserve. No cherries... 7 Agriculture 8 2010-01-01 2010-01-01 false Secondary inventory reserve. 930.57 Section 930.57... Handling Regulations § 930.57 Secondary inventory reserve. (a) In the event the inventory reserve...

Tritium release from neutron irradiated beryllium pebbles

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Werle, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reactortechnik

1998-01-01

One of the most important open issues related to beryllium for fusion applications refers to the kinetics of the tritium release as a function of neutron fluence and temperature. The EXOTIC-7 as well as the `Beryllium` experiments carried out in the HFR reactor in Petten are considered as the most detailed and significant tests for investigating the beryllium response under neutron irradiation. This paper reviews the present status of beryllium post-irradiation examinations performed at the Forschungszentrum Karlsruhe with samples from the above mentioned irradiation experiments, trying to elucidate the tritium release controlling processes. In agreement with previous studies it has been found that release starts at about 500-550degC and achieves a maximum at about 700-750degC. The observed release at about 500-550degC is probably due to tritium escaping from chemical traps, while the maximum release at about 700-750degC is due to tritium escaping from physical traps. The consequences of a direct contact between beryllium and ceramics during irradiation, causing tritium implanting in a surface layer of beryllium up to a depth of about 40 mm and leading to an additional inventory which is usually several times larger than the neutron-produced one, are also presented and the effects on the tritium release are discussed. (author)

EPA Linked Open Data: Toxics Release Inventory

Data.gov (United States)

U.S. Environmental Protection Agency — TRI is a publicly available EPA database reported annually by certain covered industry groups, as well as federal facilities. It contains information about more than...

Modeling a point-source release of 1,1,1-trichloroethane using EPA's SCREEN model

International Nuclear Information System (INIS)

Henriques, W.D.; Dixon, K.R.

1994-01-01

Using data from the Environmental Protection Agency's Toxic Release Inventory 1988 (EPA TRI88), pollutant concentration estimates were modeled for a point source air release of 1,1,1-trichloroethane at the Savannah River Plant located in Aiken, South Carolina. Estimates were calculating using the EPA's SCREEN model utilizing typical meteorological conditions to determine maximum impact of the plume under different mixing conditions for locations within 100 meters of the stack. Input data for the SCREEN model were then manipulated to simulate the impact of the release under urban conditions (for the purpose of assessing future landuse considerations) and under flare release options to determine if these parameters lessen or increase the probability of human or wildlife exposure to significant concentrations. The results were then compared to EPA reference concentrations (RfC) in order to assess the size of the buffer around the stack which may potentially have levels that exceed this level of safety

Amoco/Environmental Protection Agency Pollution Prevention Project, Yorktown refinery. Refinery release inventory. Final report

International Nuclear Information System (INIS)

Klee, H.; Kizier, G.J.; Baloo, S.; Hockman, E.L.; Couzens-Roberts, C.

1992-07-01

The report volume summarizes physical data obtained during a 2-year pollution prevention study of Amoco Oil Company's Yorktown Virginia Refinery. The study was jointly sponsored as a cooperative effort of Amoco Corporation and the United States Environmental Protection Agency. A multi-media sampling program was used to identify potential pollution sources within the Refinery. Sampling and analysis included air, surface water, groundwater, and solid waste data. Public perceptions about environmental issues of concern in the vicinity of the Refinery were also surveyed. The inventory showed that nearly 99 percent of the releases were airborne at the facility. Most of the remainder involved land disposal of solid wastes. Specific sources of major pollutants are identified

Inventory Abstraction

International Nuclear Information System (INIS)

Leigh, C.

2000-01-01

The purpose of the inventory abstraction as directed by the development plan (CRWMS M and O 1999b) is to: (1) Interpret the results of a series of relative dose calculations (CRWMS M and O 1999c, 1999d). (2) Recommend, including a basis thereof, a set of radionuclides that should be modeled in the Total System Performance Assessment in Support of the Site Recommendation (TSPA-SR) and the Total System Performance Assessment in Support of the Final Environmental Impact Statement (TSPA-FEIS). (3) Provide initial radionuclide inventories for the TSPA-SR and TSPA-FEIS models. (4) Answer the U.S. Nuclear Regulatory Commission (NRC)'s Issue Resolution Status Report ''Key Technical Issue: Container Life and Source Term'' (CLST IRSR) (NRC 1999) key technical issue (KTI): ''The rate at which radionuclides in SNF [Spent Nuclear Fuel] are released from the EBS [Engineered Barrier System] through the oxidation and dissolution of spent fuel'' (Subissue 3). The scope of the radionuclide screening analysis encompasses the period from 100 years to 10,000 years after the potential repository at Yucca Mountain is sealed for scenarios involving the breach of a waste package and subsequent degradation of the waste form as required for the TSPA-SR calculations. By extending the time period considered to one million years after repository closure, recommendations are made for the TSPA-FEIS. The waste forms included in the inventory abstraction are Commercial Spent Nuclear Fuel (CSNF), DOE Spent Nuclear Fuel (DSNF), High-Level Waste (HLW), naval Spent Nuclear Fuel (SNF), and U.S. Department of Energy (DOE) plutonium waste. The intended use of this analysis is in TSPA-SR and TSPA-FEIS. Based on the recommendations made here, models for release, transport, and possibly exposure will be developed for the isotopes that would be the highest contributors to the dose given a release to the accessible environment. The inventory abstraction is important in assessing system performance because

A break-even analysis of RFID technology for inventory sensitive to shrinkage

NARCIS (Netherlands)

Kok, de A.G.; Donselaar, van K.H.; Woensel, van T.

2008-01-01

By embedding RFID tags onto their products, both manufacturers and retailers try to control for shrinkage (e.g. due to theft). Current inventory control systems do not take into account the disappearing inventory due to this shrinkage. As a response, corrective actions are made by performing costly

Toxic releases and risk disparity: a spatiotemporal model of industrial ecology and social empowerment.

Science.gov (United States)

Aoyagi, Hannah; Ogunseitan, Oladele A

2015-06-02

Information-based regulations (IBRs) are founded on the theoretical premise that public participation in accomplishing policy goals is empowered by open access to information. Since its inception in 1988, the Toxics Release Inventory (TRI) has provided the framework and regulatory impetus for the compilation and distribution of data on toxic releases associated with industrial development, following the tenets of IBR. As TRI emissions are reputed to disproportionately affect low-income communities, we investigated how demographic characteristics are related to change in TRI emissions and toxicity risks between 1989 and 2002, and we sought to identify factors that predict these changes. We used local indicators of spatial association (LISA) maps and spatial regression techniques to study risk disparity in the Los Angeles urban area. We also surveyed 203 individuals in eight communities in the same region to measure the levels of awareness of TRI, attitudes towards air pollution, and general environmental risk. We discovered, through spatial lag models, that changes in gross and toxic emissions are related to community ethnic composition, poverty level, home ownership, and base 1989 emissions (R-square=0.034-0.083). We generated a structural equation model to explain the determinants of social empowerment to act on the basis of environmental information. Hierarchical confirmatory factor analysis (HCFA) supports the theoretical model that individual empowerment is predicted by risk perception, worry, and awareness (Chi-square=63.315, p=0.022, df=42). This study provides strong evidence that spatiotemporal changes in regional-scale environmental risks are influenced by individual-scale empowerment mediated by IBRs.

Toxic Releases and Risk Disparity: A Spatiotemporal Model of Industrial Ecology and Social Empowerment

Directory of Open Access Journals (Sweden)

Hannah Aoyagi

2015-06-01

Full Text Available Information-based regulations (IBRs are founded on the theoretical premise that public participation in accomplishing policy goals is empowered by open access to information. Since its inception in 1988, the Toxics Release Inventory (TRI has provided the framework and regulatory impetus for the compilation and distribution of data on toxic releases associated with industrial development, following the tenets of IBR. As TRI emissions are reputed to disproportionately affect low-income communities, we investigated how demographic characteristics are related to change in TRI emissions and toxicity risks between 1989 and 2002, and we sought to identify factors that predict these changes. We used local indicators of spatial association (LISA maps and spatial regression techniques to study risk disparity in the Los Angeles urban area. We also surveyed 203 individuals in eight communities in the same region to measure the levels of awareness of TRI, attitudes towards air pollution, and general environmental risk. We discovered, through spatial lag models, that changes in gross and toxic emissions are related to community ethnic composition, poverty level, home ownership, and base 1989 emissions (R-square = 0.034–0.083. We generated a structural equation model to explain the determinants of social empowerment to act on the basis of environmental information. Hierarchical confirmatory factor analysis (HCFA supports the theoretical model that individual empowerment is predicted by risk perception, worry, and awareness (Chi-square = 63.315, p = 0.022, df = 42. This study provides strong evidence that spatiotemporal changes in regional-scale environmental risks are influenced by individual-scale empowerment mediated by IBRs.

Automated Inventory Control System for Nigeria Power Holding ...

African Journals Online (AJOL)

The company may want to release some capital from its inventory investment by reducing stock levels. In addition, manual ways of handling inventory has failed to cope with factors like ... graphical interface ability for decision making.

2004 Toxic Chemical Release Inventory Report for the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Section 313

Energy Technology Data Exchange (ETDEWEB)

M. Stockton

2006-01-15

Section 313 of Emergency Planning and Community Right-to-Know Act (EPCRA) specifically requires facilities to submit a Toxic Chemical Release Inventory Report (Form R) to the U.S. Environmental Protection Agency (EPA) and state agencies if the owners and operators manufacture, process, or otherwise use any of the listed toxic chemicals above listed threshold quantities. EPA compiles this data in the Toxic Release Inventory database. Form R reports for each chemical over threshold quantities must be submitted on or before July 1 each year and must cover activities that occurred at the facility during the previous year. For reporting year 2004, Los Alamos National Laboratory (LANL or the Laboratory) submitted Form R reports for lead compounds, nitric acid, and nitrate compounds as required under the EPCRA Section 313. No other EPCRA Section 313 chemicals were used in 2004 above the reportable thresholds. This document provides a description of the evaluation of EPCRA Section 313 chemical use and threshold determinations for LANL for calendar year 2004, as well as background information about data included on the Form R reports.

INVENTORY ABSTRACTION

International Nuclear Information System (INIS)

Ragan, G.

2001-01-01

The purpose of the inventory abstraction, which has been prepared in accordance with a technical work plan (CRWMS M andO 2000e for/ICN--02 of the present analysis, and BSC 2001e for ICN 03 of the present analysis), is to: (1) Interpret the results of a series of relative dose calculations (CRWMS M andO 2000c, 2000f). (2) Recommend, including a basis thereof, a set of radionuclides that should be modeled in the Total System Performance Assessment in Support of the Site Recommendation (TSPA-SR) and the Total System Performance Assessment in Support of the Final Environmental Impact Statement (TSPA-FEIS). (3) Provide initial radionuclide inventories for the TSPA-SR and TSPA-FEIS models. (4) Answer the U.S. Nuclear Regulatory Commission (NRC)'s Issue Resolution Status Report ''Key Technical Issue: Container Life and Source Term'' (CLST IRSR) key technical issue (KTI): ''The rate at which radionuclides in SNF [spent nuclear fuel] are released from the EBS [engineered barrier system] through the oxidation and dissolution of spent fuel'' (NRC 1999, Subissue 3). The scope of the radionuclide screening analysis encompasses the period from 100 years to 10,000 years after the potential repository at Yucca Mountain is sealed for scenarios involving the breach of a waste package and subsequent degradation of the waste form as required for the TSPA-SR calculations. By extending the time period considered to one million years after repository closure, recommendations are made for the TSPA-FEIS. The waste forms included in the inventory abstraction are Commercial Spent Nuclear Fuel (CSNF), DOE Spent Nuclear Fuel (DSNF), High-Level Waste (HLW), naval Spent Nuclear Fuel (SNF), and U.S. Department of Energy (DOE) plutonium waste. The intended use of this analysis is in TSPA-SR and TSPA-FEIS. Based on the recommendations made here, models for release, transport, and possibly exposure will be developed for the isotopes that would be the highest contributors to the dose given a release

Estimating dead wood during national forest inventories: a review of inventory methodologies and suggestions for harmonization.

Science.gov (United States)

Woodall, Christopher W; Rondeux, Jacques; Verkerk, Pieter J; Ståhl, Göran

2009-10-01

Efforts to assess forest ecosystem carbon stocks, biodiversity, and fire hazards have spurred the need for comprehensive assessments of forest ecosystem dead wood (DW) components around the world. Currently, information regarding the prevalence, status, and methods of DW inventories occurring in the world's forested landscapes is scattered. The goal of this study is to describe the status, DW components measured, sample methods employed, and DW component thresholds used by national forest inventories that currently inventory DW around the world. Study results indicate that most countries do not inventory forest DW. Globally, we estimate that about 13% of countries inventory DW using a diversity of sample methods and DW component definitions. A common feature among DW inventories was that most countries had only just begun DW inventories and employ very low sample intensities. There are major hurdles to harmonizing national forest inventories of DW: differences in population definitions, lack of clarity on sample protocols/estimation procedures, and sparse availability of inventory data/reports. Increasing database/estimation flexibility, developing common dimensional thresholds of DW components, publishing inventory procedures/protocols, releasing inventory data/reports to international peer review, and increasing communication (e.g., workshops) among countries inventorying DW are suggestions forwarded by this study to increase DW inventory harmonization.

Design options to minimize tritium inventories at Savannah River

Energy Technology Data Exchange (ETDEWEB)

Klein, J.E., E-mail: james.klein@srnl.doe.gov; Wilson, J.; Heroux, K.J.; Poore, A.S.; Babineau, D.W.

2016-11-01

Highlights: • La-Ni-Al alloys are used as tritium storage materials and retain He-3. • La-Ni-Al He-3 effects decrease useable process tritium inventory. • Use of Pd or depleted uranium beds decreases process tritium inventories. • Reduced inventory tritium facilities will lower public risk. - Abstract: Large quantities of tritium are stored and processed at the Savannah River Site (SRS) Tritium Facilities. In many design basis accidents (DBAs), it is assumed the entire tritium inventory of the in-process vessels are released from the facility and the site for inclusion in public radiological dose calculations. Pending changes in public dose calculation methodologies are driving the need for smaller in-process tritium inventories to be released during DBAs. Reducing the in-process tritium inventory will reduce the unmitigated source term for public dose calculations and will also reduce the production demand for a lower inventory process. This paper discusses process design options to reduce in-process tritium inventories. A Baseline process is defined to illustrate the impact of removing or replacing La-Ni-Al alloy tritium storage beds with palladium (Pd) or depleted uranium (DU) storage beds on facility in-process tritium inventories. Elimination of La-Ni-Al alloy tritium storage beds can reduce in-process tritium inventories by over 1.5 kg, but alternate process technologies may needed to replace some functions of the removed beds.

Design options to minimize tritium inventories at Savannah River

International Nuclear Information System (INIS)

Klein, J.E.; Wilson, J.; Heroux, K.J.; Poore, A.S.; Babineau, D.W.

2016-01-01

Highlights: • La-Ni-Al alloys are used as tritium storage materials and retain He-3. • La-Ni-Al He-3 effects decrease useable process tritium inventory. • Use of Pd or depleted uranium beds decreases process tritium inventories. • Reduced inventory tritium facilities will lower public risk. - Abstract: Large quantities of tritium are stored and processed at the Savannah River Site (SRS) Tritium Facilities. In many design basis accidents (DBAs), it is assumed the entire tritium inventory of the in-process vessels are released from the facility and the site for inclusion in public radiological dose calculations. Pending changes in public dose calculation methodologies are driving the need for smaller in-process tritium inventories to be released during DBAs. Reducing the in-process tritium inventory will reduce the unmitigated source term for public dose calculations and will also reduce the production demand for a lower inventory process. This paper discusses process design options to reduce in-process tritium inventories. A Baseline process is defined to illustrate the impact of removing or replacing La-Ni-Al alloy tritium storage beds with palladium (Pd) or depleted uranium (DU) storage beds on facility in-process tritium inventories. Elimination of La-Ni-Al alloy tritium storage beds can reduce in-process tritium inventories by over 1.5 kg, but alternate process technologies may needed to replace some functions of the removed beds.

Developing Learning Style Inventory for Effective Instructional Design

Science.gov (United States)

Guven, Bulent; Ozbek, Ozge

2007-01-01

In the process of education, instead of classifying students according to their insufficiency, teachers should try to get to know them and determine their cognitive, sensorial, and kinetic characteristics. This study on improving learning style inventory, which aims to help classroom teachers determine students' attributes in individualized…

Superfund and Toxic Release Inventory Sites - MDC_ContaminatedSite

Data.gov (United States)

NSGIC Local Govt | GIS Inventory — A point feature class of open DERM Contaminated sites - see phase code for status of site. Contaminated sites identifies properties where environmental contamination...

Nuclear material inventory estimation in solvent extraction contactors

International Nuclear Information System (INIS)

Beyerlein, A.; Geldard, J.

1986-06-01

This report describes the development of simple nuclear material (uranium and plutonium) inventory relations for mixer-settler solvent extraction contactors used in reprocessing spent nuclear fuels. The relations are developed for light water reactor fuels where the organic phase is 30% tri-n-butylphosphate (TBP) by volume. For reprocessing plants using mixer-settler contactors as much as 50% of the nuclear material within the contactors is contained in A type (aqueous to organic extraction) contactors. Another very significant portion of the contactor inventory is in the partitioning contactors. The stripping contactors contain a substantial uranium inventory but contain a very small plutonium inventory (about 5 to 10% of the total contactor inventory). The simplified inventory relations developed in this work for mixer-settler contactors reproduce the PUBG databases within about a 5% standard deviation. They can be formulated to explicitly show the dependence of the inventory on nuclear material concentrations in the aqueous feed streams. The dependence of the inventory on contactor volumes, phase volume ratios, and acid and TBP concentrations are implicitly contained in parameters that can be calculated for a particular reprocessing plant from nominal flow sheet data. The terms in the inventory relations that represent the larger portion of the inventory in A type and partitioning contactors can be extended to pulsed columns virtually without change

78 FR 13743 - Department of State FY11 Service Contract Inventory

Science.gov (United States)

2013-02-28

... DEPARTMENT OF STATE [Public Notice 8207] Department of State FY11 Service Contract Inventory... Contract Inventory. SUMMARY: The Department of State has publically released its Service Contract Inventory... Act, Public Law 111-117, requires Department of State, and other civilian agencies, to submit an...

77 FR 5614 - Department of State FY11 Service Contract Inventory

Science.gov (United States)

2012-02-03

... DEPARTMENT OF STATE [Public Notice 7785] Department of State FY11 Service Contract Inventory... Contract Inventory. SUMMARY: The Department of State has publically released its Service Contract Inventory.../ . Section 743 of Division C of the FY 2010 Consolidated Appropriations Act, Public Law 111-117, requires...

76 FR 9399 - Department of State FY10 Service Contract Inventory

Science.gov (United States)

2011-02-17

... DEPARTMENT OF STATE [Public Notice 7321] Department of State FY10 Service Contract Inventory... Contract Inventory. SUMMARY: The Department of State has publically released its Service Contract Inventory for FY10. Section 743 of Division C of the FY 2010 Consolidated Appropriations Act, Public Law 111-117...

Tritium transport and release from lithium ceramic breeder materials

International Nuclear Information System (INIS)

Johnson, C.E.; Kopasz, J.P.; Tam, S.W.

1994-01-01

In an operating fusion reactor,, the tritium breeding blanket will reach a condition in which the tritium release rate equals the production rate. The tritium release rate must be fast enough that the tritium inventory in the blanket does not become excessive. Slow tritium release will result in a large tritium inventory, which is unacceptable from both economic and safety viewpoints As a consequence, considerable effort has been devoted to understanding the tritium release mechanism from ceramic breeders and beryllium neutron multipliers through theoretical, laboratory, and in-reactor studies. This information is being applied to the development of models for predicting tritium release for various blanket operating conditions

User Instructions for the Systems Assessment Capability, Rev. 0, Computer Codes Volume 1: Inventory, Release, and Transport Modules

International Nuclear Information System (INIS)

Eslinger, Paul W.; Engel, David W.; Gerhardstein, Lawrence H.; Lopresti, Charles A.; Nichols, William E.; Strenge, Dennis L.

2001-12-01

One activity of the Department of Energy's Groundwater/Vadose Zone Integration Project is an assessment of cumulative impacts from Hanford Site wastes on the subsurface environment and the Columbia River. Through the application of a system assessment capability (SAC), decisions for each cleanup and disposal action will be able to take into account the composite effect of other cleanup and disposal actions. The SAC has developed a suite of computer programs to simulate the migration of contaminants (analytes) present on the Hanford Site and to assess the potential impacts of the analytes, including dose to humans, socio-cultural impacts, economic impacts, and ecological impacts. The general approach to handling uncertainty in the SAC computer codes is a Monte Carlo approach. Conceptually, one generates a value for every stochastic parameter in the code (the entire sequence of modules from inventory through transport and impacts) and then executes the simulation, obtaining an output value, or result. This document provides user instructions for the SAC codes that handle inventory tracking, release of contaminants to the environment, and transport of contaminants through the unsaturated zone, saturated zone, and the Columbia River

An Improved Inventory Control Model for the Brazilian Navy Supply System

Science.gov (United States)

2001-12-01

Portuguese Centro de Controle de Inventario da Marinha, the Brazilian Navy Inventory Control Point (ICP) developed an empirical model called SPAADA...NAVAL POSTGRADUATE SCHOOL Monterey, California THESIS Approved for public release; distribution is unlimited AN IMPROVED INVENTORY CONTROL ...AN IMPROVED INVENTORY CONTROL MODEL FOR THE BRAZILIAN NAVY SUPPLY SYSTEM Contract Number Grant Number Program Element Number Author(s) Moreira

Effects of control technology on the projected krypton-85 environmental inventory

International Nuclear Information System (INIS)

Oscarson, E.E.

1973-01-01

Growth projections for the USA nuclear power industry may be used to make projections of future radioactive material inventories available for potential release to the environment. Since krypton-85 is produced in reactors, the potential routes of release to the environment are at the reactors or the fuel reprocessing plants. The present generation of reactors and fuel reprocessing plants do not use any systems to limit the release of krypton-85 into the biosphere. Clean-up systems are currently being designed and could be introduced when necessary. The cumulative inventory of krypton-85 in the environment is dependent upon the time of introduction of these clean-up systems and their efficiencies, in addition to the total quantity produced. Annual and cumulative inventories of krypton-85 are projected to increase dramatically over the next 50 years. If controls are assumed to be initiated at various years, a series of graphs of different cumulative environmental inventories and the associated doses and health effects are drawn. Varying the year of introduction and the efficiency of these systems allows one to speculate as to the optimum time for control implementation

Tritium inventory prediction in a CANDU plant

International Nuclear Information System (INIS)

Song, M.J.; Son, S.H.; Jang, C.H.

1995-01-01

The flow of tritium in a CANDU nuclear power plant was modeled to predict tritium activity build-up. Predictions were generally in good agreement with field measurements for the period 1983--1994. Fractional contributions of coolant and moderator systems to the environmental tritium release were calculated by least square analysis using field data from the Wolsong plant. From the analysis, it was found that: (1) about 94% of tritiated heavy water loss came from the coolant system; (2) however, about 64% of environmental tritium release came from the moderator system. Predictions of environmental tritium release were also in good agreement with field data from a few other CANDU plants. The model was used to calculate future tritium build-up and environmental tritium release at Wolsong site, Korea, where one unit is operating and three more units are under construction. The model predicts the tritium inventory at Wolsong site to increase steadily until it reaches the maximum of 66.3 MCi in the year 2026. The model also predicts the tritium release rate to reach a maximum of 79 KCi/yr in the year 2012. To reduce the tritium inventory at Wolsong site, construction of a tritium removal facility (TRF) is under consideration. The maximum needed TRF capacity of 8.7 MCi/yr was calculated to maintain tritium concentration effectively in CANDU reactors

A description of the reactor inventory module NECTAR-RICE

International Nuclear Information System (INIS)

Nair, S.

1984-06-01

This note describes the NECTAR-RICE module of the CEGB's NECTAR environmental code, which can be used to calculate the actinide and/or fission product inventories of irradiated nuclear fuel used as input to the calculation of the release source term to atmosphere for accidental releases. The range of actinide and fission product nuclides considered is large enough to permit studies to be made for virtually any irradiation history consisting of ad hoc combinations of irradiation and cooling periods. The actinide and fission product inventories are calculated for burnup periods using numerical methods best suited to this problem, while analytical solutions are used for cooling periods. The code can be used to perform a coupled actinide-fission product calculation, a solely actinide calculation or a solely fission product calculation. Output consists of inventories, activities, and γ spectra, among others. A brief description is also given of previous work in this field. (author)

Measurement of the gap and grain boundary inventories of Cs, Sr and I in domestic used PWR fuels

International Nuclear Information System (INIS)

Kim, S. S.; Choi, J. W.; Seo, H. S.; Cho, W. J.; Kang, K. C.; Kwon, S. H.

2007-01-01

Inventories of soluble elements in the gap and grain boundaries of domestic used PWR fuel pellets were measured to estimate the quantities of radionuclides that are liable to be rapidly released into the groundwater of a disposal site. The gap inventory of cesium for the pellets in the used fuel with a burn-up range of 45 to 66 GWD/MTU showed 0.85 to 1.7% of its total inventory, which was close to 1/6 to 1/3 of the fission gas release fraction (FGRF). However, the amounts of cesium released from the gaps of the pellets below 40 GWD/MTU of a burn-up and less than 1% FGRF were so erratic that the gap inventory could not be defined by its FGRF. Strontium inventories in the gap and grain boundaries of the pellets in the same rod were not significantly varied, and the iodine inventory in the gap of the used PWR fuels was estimated to be less than or the same as the FGRF

Quantitative Analysis of Kr-85 Fission Gas Release from Dry Process for the Treatment of Spent PWR Fuel

International Nuclear Information System (INIS)

Park, Geun Il; Cho, Kwang Hun; Lee, Dou Youn; Lee, Jung Won; Park, Jang Jin; Song, Kee Chan

2007-01-01

As spent UO 2 fuel oxidizes to U 3 O 8 by air oxidation, a corresponding volume expansion separate grains, releasing the grain-boundary inventory of fission gases. Fission products in spent UO 2 fuel can be distributed in three major regions : the inventory in fuel-sheath gap, the inventory on grain boundaries and the inventory in UO 2 matrix. Release characteristic of fission gases depends on its distribution amount in three regions as well as spent fuel burn-up. Oxidation experiments of spent fuel at 500 .deg. C gives the information of fission gases inventory in spent fuel, and further annealing experiments at higher temperature produces matrix inventory of fission gases on segregated grain. In previous study, fractional release characteristics of Kr- 85 during OREOX (Oxidation and REduction of Oxide fuel) treatment as principal key process for recycling spent PWR fuel via DUPIC cycle have already evaluated as a function of fuel burn-up with 27.3, 35 and 65 MWd/tU. In this paper, new release experiment results of Kr-85 using spent fuel with burn- up of 58 GWd/tU are included to evaluate the fission gas release behavior. As a point of summary in fission gases release behavior, the quantitative analysis of Kr- 85 release characteristics from various spent fuels with different burn-up during voloxidation and OREOX process were reviewed

Inventory of Engineered Nanoparticle-Containing Consumer Products Available in the Singapore Retail Market and Likelihood of Release into the Aquatic Environment.

Science.gov (United States)

Zhang, Yuanyuan; Leu, Yu-Rui; Aitken, Robert J; Riediker, Michael

2015-07-24

Consumer products containing engineered nanoparticles (ENP) are already entering the marketplace. This leads, inter alia, to questions about the potential for release of ENP into the environment from commercial products. We have inventoried the prevalence of ENP-containing consumer products in the Singapore market by carrying out onsite assessments of products sold in all major chains of retail and cosmetic stores. We have assessed their usage patterns and estimated release factors and emission quantities to obtain a better understanding of the quantities of ENP that are released into which compartments of the aquatic environment in Singapore. Products investigated were assessed for their likelihood to contain ENP based on the declaration of ENP by producers, feature descriptions, and the information on particle size from the literature. Among the 1,432 products investigated, 138 were "confirmed" and 293 were "likely" to contain ENP. Product categories included sunscreens, cosmetics, health and fitness, automotive, food, home and garden, clothing and footwear, and eyeglass/lens coatings. Among the 27 different types of nanomaterials identified, SiO2 was predominant, followed by TiO2 and ZnO, Carbon Black, Ag, and Au. The amounts of ENP released into the aquatic system, which was estimated on the basis of typical product use, ENP concentration in the product, daily use quantity, release factor, and market share, were in the range of several hundred tons per year. As these quantities are likely to increase, it will be important to further study the fate of ENP that reach the aquatic environment in Singapore.

Inventory of Engineered Nanoparticle-Containing Consumer Products Available in the Singapore Retail Market and Likelihood of Release into the Aquatic Environment

Directory of Open Access Journals (Sweden)

Yuanyuan Zhang

2015-07-01

Full Text Available Consumer products containing engineered nanoparticles (ENP are already entering the marketplace. This leads, inter alia, to questions about the potential for release of ENP into the environment from commercial products. We have inventoried the prevalence of ENP-containing consumer products in the Singapore market by carrying out onsite assessments of products sold in all major chains of retail and cosmetic stores. We have assessed their usage patterns and estimated release factors and emission quantities to obtain a better understanding of the quantities of ENP that are released into which compartments of the aquatic environment in Singapore. Products investigated were assessed for their likelihood to contain ENP based on the declaration of ENP by producers, feature descriptions, and the information on particle size from the literature. Among the 1,432 products investigated, 138 were “confirmed” and 293 were “likely” to contain ENP. Product categories included sunscreens, cosmetics, health and fitness, automotive, food, home and garden, clothing and footwear, and eyeglass/lens coatings. Among the 27 different types of nanomaterials identified, SiO2 was predominant, followed by TiO2 and ZnO, Carbon Black, Ag, and Au. The amounts of ENP released into the aquatic system, which was estimated on the basis of typical product use, ENP concentration in the product, daily use quantity, release factor, and market share, were in the range of several hundred tons per year. As these quantities are likely to increase, it will be important to further study the fate of ENP that reach the aquatic environment in Singapore.

Consequences of severe radioactive releases to Nordic Marine environment

DEFF Research Database (Denmark)

Iosjpe, M.; Isaksson, M.; Joensen, H.P.

- or minor – radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MWth reactor size were used. Based on source term analyses, the chosen release fractions in the study were: iodine 20% (of the total core inventory), caesium 10%, tellurium 10%, strontium 0...

Electrospun pH-sensitive core-shell polymer nanocomposites fabricated using a tri-axial process.

Science.gov (United States)

Yang, Chen; Yu, Deng-Guang; Pan, Deng; Liu, Xin-Kuan; Wang, Xia; Bligh, S W Annie; Williams, Gareth R

2016-04-15

A modified tri-axial electrospinning process was developed for the generation of a new type of pH-sensitive polymer/lipid nanocomposite. The systems produced are able to promote both dissolution and permeation of a model poorly water-soluble drug. First, we show that it is possible to run a tri-axial process with only one of the three fluids being electrospinnable. Using an electrospinnable middle fluid of Eudragit S100 (ES100) with pure ethanol as the outer solvent and an unspinnable lecithin-diclofenac sodium (PL-DS) core solution, nanofibers with linear morphology and clear core/shell structures can be fabricated continuously and smoothly. X-ray diffraction proved that these nanofibers are structural nanocomposites with the drug present in an amorphous state. In vitro dissolution tests demonstrated that the formulations could preclude release in acidic conditions, and that the drug was released from the fibers in two successive steps at neutral pH. The first step is the dissolution of the shell ES100 and the conversion of the core PL-DS into sub-micron sized particles. This frees some DS into solution, and later the remaining DS is gradually released from the PL-DS particles through diffusion. Ex vivo permeation results showed that the composite nanofibers give a more than twofold uplift in the amount of DS passing through the colonic membrane as compared to pure DS; 74% of the transmitted drug was in the form of PL-DS particles. The new tri-axial electrospinning process developed in this work provides a platform to fabricate structural nanomaterials, and the core-shell polymer-PL nanocomposites we have produced have significant potential applications for oral colon-targeted drug delivery. A modified tri-axial electrospinning is demonstrated to create a new type of core-shell pH-sensitive polymer/lipid nanocomposites, in which an electrospinnable middle fluid is exploited to support the un-spinnable outer and inner fluids. The structural nanocomposites are able

Regulation through revelation: the origin, politics, and impacts of the Toxics Release Inventory Program

National Research Council Canada - National Science Library

Hamilton, James

2005-01-01

... of the TRI from its origin and implementation to its revision and retrenchment. The mix of case study and quantitative analysis shows how the TRI operates and how the information provided affects decisions in both the public and private sectors. The lessons drawn about the operation of information provision programs should be of interest to multiple audi...

Fabrication of planar, layered nanoparticles using tri-layer resist templates.

Science.gov (United States)

Hu, Wei; Zhang, Mingliang; Wilson, Robert J; Koh, Ai Leen; Wi, Jung-Sub; Tang, Mary; Sinclair, Robert; Wang, Shan X

2011-05-06

A simple and universal pathway to produce free multilayer synthetic nanoparticles is developed based on lithography, vapor phase deposition and a tri-layer resist lift-off and release process. The fabrication method presented in this work is ideal for production of a broad range of nanoparticles, either free in solution or still attached to an intact release layer, with unique magnetic, optical, radioactive, electronic and catalytic properties. Multi-modal capabilities are implicit in the layered architecture. As an example, directly fabricated magnetic nanoparticles are evaluated to illustrate the structural integrity of thin internal multilayers and the nanoparticle stability in aggressive biological environments, which is highly desired for biomedical applications.

Validity of the Parental Burnout Inventory Among Dutch Employees.

Science.gov (United States)

Van Bakel, Hedwig J A; Van Engen, Marloes L; Peters, Pascale

2018-01-01

The purpose of this study was to validate the Parental Burnout Inventory (PBI) in a Dutch sample of working parents. The Dutch version of the PBI and questionnaires about work were administered to 627 working parents, with at least one child living at home. We investigated whether the tri-dimensional structure of the PBI held in a sample of male and female employed parents. Furthermore, we examined the relationships between PBI and the constructs work-related burnout, depressive mood, parenting stress and work-family conflict, which we assessed with widely used and validated instruments, i.e., emotional exhaustion [a subscale of the Dutch version of Maslach's Burnout Inventory], a Dutch Parental Stress Questionnaire and Work-Family Conflict. The results support the validity of a tri-dimensional parental burnout syndrome, including exhaustion, distancing and inefficacy. Low to moderate correlations between parents' burnout symptoms and professional exhaustion, parenting stress, depressive complaints and work-family conflict experiences were found, suggesting that the concept of PBI differs significantly from the concepts of job burnout, depression and stress, respectively. The current study confirms that some parents are extremely exhausted by their parental role. However, the number of Dutch employees reporting extreme parental burnout is rather low.

Validity of the Parental Burnout Inventory Among Dutch Employees

Directory of Open Access Journals (Sweden)

Hedwig J. A. Van Bakel

2018-05-01

Full Text Available The purpose of this study was to validate the Parental Burnout Inventory (PBI in a Dutch sample of working parents. The Dutch version of the PBI and questionnaires about work were administered to 627 working parents, with at least one child living at home. We investigated whether the tri-dimensional structure of the PBI held in a sample of male and female employed parents. Furthermore, we examined the relationships between PBI and the constructs work-related burnout, depressive mood, parenting stress and work-family conflict, which we assessed with widely used and validated instruments, i.e., emotional exhaustion [a subscale of the Dutch version of Maslach’s Burnout Inventory], a Dutch Parental Stress Questionnaire and Work-Family Conflict. The results support the validity of a tri-dimensional parental burnout syndrome, including exhaustion, distancing and inefficacy. Low to moderate correlations between parents’ burnout symptoms and professional exhaustion, parenting stress, depressive complaints and work-family conflict experiences were found, suggesting that the concept of PBI differs significantly from the concepts of job burnout, depression and stress, respectively. The current study confirms that some parents are extremely exhausted by their parental role. However, the number of Dutch employees reporting extreme parental burnout is rather low.

COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

Energy Technology Data Exchange (ETDEWEB)

S.O. Bader

1999-10-18

The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be

COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

International Nuclear Information System (INIS)

S.O. Bader

1999-01-01

The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be

2002 Toxic Chemical Release Inventory Report for the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Section 313

International Nuclear Information System (INIS)

Stockton, M.

2003-01-01

For reporting year 2002, Los Alamos National Laboratory (LANL or the Laboratory) submitted Form R reports for lead compounds and mercury as required under the Emergency Planning and Community Right-to-Know Act (EPCRA), Section 313. No other EPCRA Section 313 chemicals were used in 2002 above the reportable thresholds. This document was prepared to provide a description of the evaluation of EPCRA Section 313 chemical usage and threshold determinations for LANL for calendar year 2002 as well as provide background information about the data included on the Form R reports. Section 313 of EPCRA specifically requires facilities to submit a Toxic Chemical Release Inventory report (Form R) to the U.S. Environmental Protection Agency (EPA) and state agencies if the owners and operators manufacture, process, or otherwise use any of the listed toxic chemicals above listed threshold quantities. EPA compiles this data in the Toxic Release Inventory database. Form R reports for each chemical over threshold quantities must be submitted on or before July 1 each year and must cover activities that occurred at the facility during the previous year. In 1999 EPA promulgated a final rule on Persistent Bioaccumulative Toxics (PBTs). This rule added several chemicals to the EPCRA Section 313 list of toxic chemicals and established lower reporting thresholds for these and other PBT chemicals that were already reportable under EPCRA Section 313. These lower thresholds became applicable in reporting year 2000. In 2001, EPA expanded the PBT rule to include a lower reporting threshold for lead and lead compounds. Facilities that manufacture, process, or otherwise use more than 100 lb of lead or lead compounds must submit a Form R

2006 Toxic Chemical Release Inventory Report for the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Section 313

Energy Technology Data Exchange (ETDEWEB)

Ecology and Air Quality Group (ENV-EAQ)

2007-12-12

For reporting year 2006, Los Alamos National Laboratory (LANL or the Laboratory) submitted Form R reports for lead as required under the Emergency Planning and Community Right-to-Know Act (EPCRA) Section 313. No other EPCRA Section 313 chemicals were used in 2006 above the reportable thresholds. This document was prepared to provide a description of the evaluation of EPCRA Section 313 chemical use and threshold determinations for LANL for calendar year 2006, as well as to provide background information about data included on the Form R reports. Section 313 of EPCRA specifically requires facilities to submit a Toxic Chemical Release Inventory Report (Form R) to the U.S. Environmental Protection Agency (EPA) and state agencies if the owners and operators manufacture, process, or otherwise use any of the listed toxic chemicals above listed threshold quantities. EPA compiles this data in the Toxic Release Inventory database. Form R reports for each chemical over threshold quantities must be submitted on or before July 1 each year and must cover activities that occurred at the facility during the previous year. In 1999, EPA promulgated a final rule on persistent bioaccumulative toxics (PBTs). This rule added several chemicals to the EPCRA Section 313 list of toxic chemicals and established lower reporting thresholds for these and other PBT chemicals that were already reportable. These lower thresholds became applicable in reporting year 2000. In 2001, EPA expanded the PBT rule to include a lower reporting threshold for lead and lead compounds. Facilities that manufacture, process, or otherwise use more than 100 lb of lead or lead compounds must submit a Form R.

Global radioxenon emission inventory based on nuclear power reactor reports.

Science.gov (United States)

Kalinowski, Martin B; Tuma, Matthias P

2009-01-01

Atmospheric radioactivity is monitored for the verification of the Comprehensive Nuclear-Test-Ban Treaty, with xenon isotopes 131mXe, 133Xe, 133mXe and 135Xe serving as important indicators of nuclear explosions. The treaty-relevant interpretation of atmospheric concentrations of radioxenon is enhanced by quantifying radioxenon emissions released from civilian facilities. This paper presents the first global radioxenon emission inventory for nuclear power plants, based on North American and European emission reports for the years 1995-2005. Estimations were made for all power plant sites for which emission data were unavailable. According to this inventory, a total of 1.3PBq of radioxenon isotopes are released by nuclear power plants as continuous or pulsed emissions in a generic year.

Low and intermediate level waste in SFR-1. Reference waste inventory

International Nuclear Information System (INIS)

Riggare, P.; Johansson, Claes

2001-06-01

The objective with this report is to describe all the waste and the waste package that is expected to be deposited in SFR-1 at the time of closure. This report is a part of the SAFE project (Safety Assessment of Final Repository for Radioactive Operational Waste), i.e. the renewed safety assessment of SFR-1. The accounted waste inventory has been used as input to the release calculation that has been performed in the SAFE project. The waste inventory is based on an estimated operational lifetime of the Swedish nuclear power plants of 40 years and that closure of the SFR repository will happen in 2030. In the report, data about geometries, weights, materials, chemicals and radionuclide are given. No chemo toxic material has been identified in the waste. The inventory is based on so called waste types and the waste types reference waste package. The reference waste package combined with a prognosis of the number of waste packages to the year 2030 gives the final waste inventory for SFR-1. All reference waste packages are thoroughly described in the appendices of this report. The reference waste packages are as far as possible based on actual experiences and measurements. The radionuclide inventory is also based on actual measurements. The inventory is based on measurements of 60 Co and 137 Cs in waste packages and on measurements 239 Pu and 240 Pu in reactor water. Other nuclides in the inventory are calculated with correlation factors. In the SAFE project's prerequisites it was said that one realistic and one conservative (pessimistic) inventory should be produced. The conservative one should then be used for the release calculations. In this report one realistic and one conservative radionuclide inventory is presented. The conservative one adds up to 10 16 Bq. Regarding materials there is only one inventory given since it is not certain what is a conservative assumption

Water Pollution Search | ECHO | US EPA

Science.gov (United States)

The Water Pollution Search within the Water Pollutant Loading Tool gives users options to search for pollutant loading information from Discharge Monitoring Report (DMR) and Toxic Release Inventory (TRI) data.

A recommended approach to the National Pollutant Release Inventory (NPRI) for the upstream oil and gas industry : 2002 : CAC emissions

International Nuclear Information System (INIS)

2003-04-01

The National Pollutant Release Inventory (NPRI) is a database of annual releases to air, water, land and off-site transfers of 273 specified pollutants. Environment Canada requires that the NPRI be reported annually. Criteria Air Contaminants (CAC) had to be reported for the first time in 2002. Air pollutants that contribute to the formation of ground level ozone and smog are included in the definition of CAC, along with any eye or respiratory irritants to both humans and animals. The substances of special interest to the petroleum industry are: oxides of nitrogen, sulphur dioxide, carbon monoxide, volatile organic compounds, total particulate matter, and particulate matters. This guide is intended to provide member companies of Canadian Association of Petroleum Producers (CAPP), operating upstream oil and gas facilities, with readily available data to determine the amount of CAC emissions released from their processes and equipment. Companies using these guidelines will be able to compare the performance of various upstream oil and gas companies more readily because the data is consistent. The scope of the project was described in section 1, and the sources of CAC emissions were identified in section 2. The reporting threshold was discussed in section 3. Data required for collection was outlined in section 4. Section 5 outlines how CAC emission quantities are determined. Calculation examples were provided in section 6 and definitions provided in section 7. 11 tabs., 1 fig

Effects of sorption hysteresis on radionuclide releases from waste packages

International Nuclear Information System (INIS)

Barney, G.S.; Reed, D.T.

1985-01-01

A one-dimensional, numerical transport model was used to calculate radionuclide releases from waste packages emplaced in a nuclear waste repository in basalt. The model incorporates both sorption and desorption isotherm parameters measured previously for sorption of key radionuclides on the packing material component of the waste package. Sorption hysteresis as described by these isotherms lowered releases of some radionuclides by as much as two orders of magnitude. Radionuclides that have low molar inventories (relative to uranium), high solubility, and strongly sorbed, are most affected by sorption hysteresis. In these cases, almost the entire radionuclide inventory is sorbed on the packing material. The model can be used to help optimize the thickness of the packing material layer by comparing release rate versus packing material thickness curves with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) release limits

Monetary Policy, Debt and the Cyclical Behavior of Inventories

Directory of Open Access Journals (Sweden)

Abdul Ghafar Ismail

2007-01-01

Full Text Available An earlier study on the determinants of inventories investment has been proposed by Lovel (1961. However, the study fails to mention the effects of financial variables. The puzzle prevails on account of imperfect capital markets. This implies that interest rate generally affects inventory investment indirectly through the debt channel. For instance, in the period of tight monetary policy, increasing interest rates have a negative impact on the present value of firms’ collateralizable net worth. In addition, they also weaken firms’ balance sheets as interest expenses also rise up. In imperfect capital markets, this fact indicates an increase in the amount of external financing that firms need, a rise in the premium on external financing that they face, and a reduction in their accumulation of assets, their spending and their production. Given the low adjustment cost that characterizes firms, it will be inventories that firms will initially reduce. Therefore, this paper is contributes to the issue of monetary policy transmission in Malaysia. Our specific attention is limited to the channel of monetary policy on a firm’s inventory. Using micro data, we try to take into account the relevance of the firm’s balance sheet conditions in the transmission of monetary policy.

Gas generation in SFL 3-5 and effects on radionuclide release

International Nuclear Information System (INIS)

Skagius, K.; Lindgren, M.; Pers, K.

1999-12-01

A deep repository, SFL 3-5, is presently planned for disposing of long-lived low- and intermediate-level waste. In this study the amounts of gas that can be generated in the waste packages and in the vaults are estimated. The potential gas pressure build-up, the displacement of contaminated water and the consequences on radionuclide release from the engineered barriers in the repository are also addressed. The study is focussed on the repository design and waste inventory that was defined for the prestudy of SFL 3-5. Since the reporting of the prestudy the design of the repository has been modified and the waste inventory has been updated and a preliminary safety assessment of the repository has been carried out based on the new design and updated waste inventory. The implications on gas generation and release of these modifications in design and waste inventory are briefly addressed in this study

Gas generation in SFL 3-5 and effects on radionuclide release

Energy Technology Data Exchange (ETDEWEB)

Skagius, K.; Lindgren, M.; Pers, K. [Kemakta Konsult AB, Stockholm (Sweden)

1999-12-01

A deep repository, SFL 3-5, is presently planned for disposing of long-lived low- and intermediate-level waste. In this study the amounts of gas that can be generated in the waste packages and in the vaults are estimated. The potential gas pressure build-up, the displacement of contaminated water and the consequences on radionuclide release from the engineered barriers in the repository are also addressed. The study is focussed on the repository design and waste inventory that was defined for the prestudy of SFL 3-5. Since the reporting of the prestudy the design of the repository has been modified and the waste inventory has been updated and a preliminary safety assessment of the repository has been carried outbased on the new design and updated waste inventory. The implications on gas generation and release of these modifications in design and waste inventory are briefly addressed in this study.

A consumption-based GHG inventory for the U.S. state of Oregon.

Science.gov (United States)

Erickson, Peter; Allaway, David; Lazarus, Michael; Stanton, Elizabeth A

2012-04-03

Many U.S. states conduct greenhouse gas (GHG) inventories to inform their climate change planning efforts. These inventories usually follow a production-based method adapted from the Intergovernmental Panel on Climate Change. States could also take a consumption-based perspective, however, and estimate all emissions released to support consumption in their state, regardless of where the emissions occur. In what may be the first such comprehensive inventory conducted for a U.S. state, we find that consumption-based emissions for Oregon are 47% higher than those released in-state. This finding implies that Oregon's contribution to global greenhouse gas emissions (carbon footprint) is considerably higher than traditional production-based methods would suggest. Furthermore, the consumption-based inventory helps highlight the role of goods and services (and associated purchasing behaviors) more so than do production-based methods. Accordingly, a consumption-based perspective opens new opportunities for many states and their local government partners to reduce GHG emissions, such as initiatives to advance lower-carbon public sector or household consumption, that are well within their sphere of influence. State and local governments should consider conducting consumption-based GHG inventories and adopting consumption-based emission reductions targets in order to broaden the reach and effectiveness of state and local actions in reducing global GHG emissions. Consumption-based frameworks should be viewed as a complement to, but not a substitute for, production-based (in-state) GHG emissions inventories and targets.

Release of segregated nuclides from spent fuel

Energy Technology Data Exchange (ETDEWEB)

Johnson, L.H.; Tait, J.C. [Atomic Energy Canada Ltd., Pinawa, MB (Canada). Whiteshell Laboratories

1997-10-01

The potential release of fission and activation products from spent nuclear fuel into groundwater after container failure in the Swedish deep repository is discussed. Data from studies of fission gas release from representative Swedish BWR fuel are used to estimate the average fission gas release for the spent fuel population. Information from a variety of leaching studies on LWR and CANDU fuel are then reviewed as a basis for estimating the fraction of the inventory of key radionuclides that could be released preferentially (the Instant Release Fraction of IRF) upon failure of the fuel cladding. The uncertainties associated with these estimates are discussed. 33 refs, 6 figs, 3 tabs.

Commercial SNF Accident Release Fractions

Energy Technology Data Exchange (ETDEWEB)

J. Schulz

2004-11-05

The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the

Commercial SNF Accident Release Fractions

International Nuclear Information System (INIS)

Schulz, J.

2004-01-01

The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M andO 1999). In contrast to bare unconfined fuel assemblies, the

Inventory of accidents and losses at sea involving radioactive material

International Nuclear Information System (INIS)

2001-09-01

The present report describes the content of the inventory of accidents and losses at sea involving radioactive material. It covers accidents and losses resulting in the actual release of radioactive materials into the marine environment and also those which have the potential for release. For completeness, records of radioactive materials involved in accidents but which were recovered intact from the sea are also reported. Information on losses of sealed sources resulting in actual or potential release of activity to the marine environment nad of sealed sources that were recovered intact is also presented

The estimation and prediction of the inventories for the liquid and gaseous radwaste systems using the linear regression analysis

International Nuclear Information System (INIS)

Kim, J. Y.; Shin, C. H.; Kim, J. K.; Lee, J. K.; Park, Y. J.

2003-01-01

The variation transitions of the inventories for the liquid radwaste system and the radioactive gas have being released in containment, and their predictive values according to the operation histories of Yonggwang(YGN) 3 and 4 were analyzed by linear regression analysis methodology. The results show that the variation transitions of the inventories for those systems are linearly increasing according to the operation histories but the inventories released to the environment are considerably lower than the recommended values based on the FSAR suggestions. It is considered that some conservation were presented in the estimation methodology in preparing stage of FSAR

Calculation of the inventory and near-field release rates of radioactivity from neutron-activated metal parts discharged from the high flux isotope reactor and emplaced in solid waste storage area 6 at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Kelmers, A.D.; Hightower, J.R.

1987-05-01

Emplacement of contaminated reactor components involves disposal in lined and unlined auger holes in soil above the water table. The radionuclide inventory of disposed components was calculated. Information on the composition and weight of the components, as well as reasonable assumptions for the neutron flux fueling use, the time of neutron exposure, and radioactive decay after discharge, were employed in the inventory calculation. Near-field release rates of /sup 152/Eu, /sup 154/Eu, and /sup 155/Eu from control plates and cylinders were calculated for 50 years after emplacement. Release rates of the europium isotopes were uncertain. Two release-rate-limiting models were considered and a range of reasonable values were assumed for the time-to-failure of the auger-hole linear and aluminum cladding and europium solubility in SWSA-6 groundwater. The bounding europium radionuclide near-field release rates peaked at about 1.3 Ci/year total for /sup 152,154,155/Eu in 1987 for the lower bound, and at about 420 Ci/year in 1992 for the upper bound. The near-field release rates of /sup 55/Fe, /sup 59/Ni, /sup 60/Co, and /sup 63/Ni from stainless steel and cobalt alloy components, as well as of /sup 10/Be, /sup 41/Ca, and /sup 55/Fe from beryllium reflectors, were calculated for the next 100 years, assuming bulk waste corrosion was the release-rate-limiting step. Under the most conservative assumptions for the reflectors, the current (1986) total radionuclide release rate was calculated to be about 1.2 x 10/sup -4/ Ci/year, decreasing by 1992 to a steady release of about 1.5 x 10/sup -5/ Ci/year due primarily to /sup 41/Ca. 50 refs., 13 figs., 8 tabs.

Licensed-fuel-facility status report, inventory difference data January 1981-June 1981

International Nuclear Information System (INIS)

1982-07-01

NRC is committed to the periodic release of inventory difference data from the licensed fuel facilities after the agency has had an opportunity to review the data and has performed any related investigations associated with the data. Information included in this report includes inventory difference data for active fuel fabrication facilities possessing more than one effective kilogram of high enriched uranium, low enriched uranium, plutonium, or uranium-233

Optimization Policy of Inventory Spare Parts Stocking and Provisioning

International Nuclear Information System (INIS)

Yun, Tae Sik; Park, Jong Hyuk; Hwang, Eui Youp; Yoo, Sung Soo; Kim, In Hwan

2005-01-01

Spare parts, especially safety related items, being used in Korea Nuclear Power Plants are largely from the United States, Canada, France and the like, meaning the inventory policy, stocking and provision, should be influenced by those countries' nuclear industry situation in a direct or indirect manner. As a result of nuclear industry downturn practices, lots of spare supply corporations have gone broke, which gave immediate signals we have to resolve inventory purchases in need. It is known for that nuclear maintenance spare items are particularly composed of many kinds with small quantities, which makes matters worse to Korea nuclear operation company (KHNP) to purchase them. Hence, Korea nuclear business is trying to change its exinventory purchasing paradigm into innovative schemes it did not have to consider in the past. In order to implement a new stocking policy, it should be kept in mind the factors such as not only how much to stock for a smooth operation but also economic point of view. Even though it has done a lot of studies to optimize the inventory stocking level in an academic curiosity, it is not easy to apply the researches in a real world. Since it is so tough job to anticipate when and how large scale even occurs. Hence, it would be thought that the nuclear inventory should be dealt in a different manner from the general manufacturing industry

PENGENDALIAN PERSEDIAAN MENGGUNAKAN PENDEKATAN DYNAMIC INVENTORY DENGAN MEMPERTIMBANGKAN KETIDAKPASTIAN PERMINTAAN, YIELD, DAN LEADTIME

Directory of Open Access Journals (Sweden)

Sri Hartini

2012-01-01

Inventory, Dynamic Inventory     Abstract    Inventory management is one of serious problem faced by companies. PT Garuda Putra – Putri Jaya (PT GPPJ Pati is company which produce snack, like coated peanuts, soybean snack, and pillus. With a purpose to support production’s fluency which is afected in consumer demand fulfillment’ fluency, then PT GPPJ Pati management try to assure the availability of roll pack material. But, the failure in inventory management causing overstock in inventory of roll pack material which showed in high value of Days of Inventory (DOI. Based from preliminary research for knowing factors that affected to higher value of DOI, was concluded that the higher value of DOI caused by determination of order quantity that only consider farecast of roll pack material’s need, quantity of safety stock, and outstanding inventory in warehouse without calcuation process and still using intuition and experience of worker. Based form preliminary research, this research try to compared inventory control policy used by company (current policy, and  ( inventory model based form forecasting with uncertainty demand, yield, and lead time which developed by Mohammed Zied Babai [Baba06]. Study of policy comparison was done with implementation of spreadsheet simulation with two policy scenario. From this simulation and policy analysis, was concluded that scenario 2 is best inventory control policy because deliver smallest DOI value, i.e. 36.02 days, and lowest inventory cost, i.e. Rp 5,775,116.41. Key words : Uncertainty Lead Time, Uncertainty Demand, Uncertainty Yield, Days of Inventory, Dynamic Inventory

Update and improvement of the global krypton-85 emission inventory

International Nuclear Information System (INIS)

Ahlswede, Jochen; Hebel, Simon; Ross, J. Ole; Schoetter, Robert; Kalinowski, Martin B.

2013-01-01

Krypton-85 is mainly produced in nuclear reactors by fission of uranium and plutonium and released during chopping and dissolution of spent fuel rods in nuclear reprocessing facilities. As noble gas it is suited as a passive tracer for evaluation of atmospheric transport models. Furthermore, research is ongoing to assess its quality as an indicator for clandestine reprocessing activities. This paper continues previous efforts to compile a comprehensive historic emission inventory for krypton-85. Reprocessing facilities are the by far largest emitters of krypton-85. Information on sources and calculations used to derive the annual krypton-85 emission is provided for all known reprocessing facilities in the world. In addition, the emission characteristics of two plants, Tokai (Japan) and La Hague (France), are analysed in detail using emission data with high temporal resolution. Other types of krypton-85 sources are power reactors, naval reactors and isotope production facilities. These sources contribute only little or negligible amounts of krypton-85 compared to the large reprocessing facilities. Taking the decay of krypton-85 into account, the global atmospheric inventory is estimated to about 5500 PBq at the end of 2009. The correctness if the inventory has been proven by meteorological simulations and its error is assumed to be in the range of a few percent. - Highlights: ► Krypton-85 is mainly produced in nuclear reactors and released during reprocessing. ► Krypten-85 can be possibly used as an indicator for clandestine reprocessing. ► This work provides an up-to-date global krypton-85 emission inventory. ► The inventory includes emissions from all possible artificial sources.

Inventory of radioactive corrosion products on the primary surfaces and release during shutdown in Ringhals 2

International Nuclear Information System (INIS)

Aronsson, O.

1994-01-01

In Ringhals 2 a retrospective study using gamma scans of system surfaces, fuel crud sampling and reactor coolant analyses during operation and shutdown has been done. The data have been used to prepare a balance of activity inventory. The inventory has been fairly stable from 1986 to 1993, expressed as a gamma source term. The steam generator replacement in 1989 removed some 40-50% of the Co-60 inventory in the reactor system. After the steam generator replacement, the gamma source term has got an increasing contribution from Co-58, absolutely as well as relatively. The reason for this is probably the switch from high pH operation to modified pH operation. Corrosion from fresh alloy 690 surfaces in the new steam generators is probably another contributing factor. The inventory and production rate of Co-60 is decreasing over the years. It has also been found that clean-up of the reactor coolant during start-up, operation, and shutdown as well as the fuel pool during refuelling removes about the same amounts of Co-60. (author). 11 figs., 15 refs

Experiments to Measure Hydrogen Release from Graphite Walls During Disruptions in DIII-D

International Nuclear Information System (INIS)

Hollmann, E.M.; Pablant, N.A.; Rudakov, D.L.; Boedo, J.A.; Brooks, N.H.; Jernigan, Thomas C.; Pigarov, A.Y.

2009-01-01

Spectroscopy and wall the bake-out measurements are performed in the DIII-D tokamak to estimate the amount of hydrogen stored in and released from the walls during disruptions. Both naturally occurring disruptions and disruptions induced by massive gas injection (MGI) are investigated. The measurements indicate that both types of disruptions cause a net release of order 10(21) hydrogen (or deuterium) atoms from the graphite walls. This is comparable to the pre-disruptions plasma particle inventory, so the released hydrogen is important for accurate modeling of disruptions. However, the amount of hydrogen released is small compared to the total saturated wall inventory of order 10(22)-10(23), So it appears that many disruptions are necessary to provide full pump-out of the vessel walls. (C) 2009 Published by Elsevier B.V.

An OMIC biomarker detection algorithm TriVote and its application in methylomic biomarker detection.

Science.gov (United States)

Xu, Cheng; Liu, Jiamei; Yang, Weifeng; Shu, Yayun; Wei, Zhipeng; Zheng, Weiwei; Feng, Xin; Zhou, Fengfeng

2018-04-01

Transcriptomic and methylomic patterns represent two major OMIC data sources impacted by both inheritable genetic information and environmental factors, and have been widely used as disease diagnosis and prognosis biomarkers. Modern transcriptomic and methylomic profiling technologies detect the status of tens of thousands or even millions of probing residues in the human genome, and introduce a major computational challenge for the existing feature selection algorithms. This study proposes a three-step feature selection algorithm, TriVote, to detect a subset of transcriptomic or methylomic residues with highly accurate binary classification performance. TriVote outperforms both filter and wrapper feature selection algorithms with both higher classification accuracy and smaller feature number on 17 transcriptomes and two methylomes. Biological functions of the methylome biomarkers detected by TriVote were discussed for their disease associations. An easy-to-use Python package is also released to facilitate the further applications.

PyTRiP - a toolbox and GUI for the proton/ion therapy planning system TRiP

International Nuclear Information System (INIS)

Toftegaard, J; Bassler, N; Petersen, J B

2014-01-01

Purpose: Only very few treatment planning systems (TPS) are capable of handling heavy ions. Commercial heavy ion TPS are costly and normally restrict the possibility to implement new functionalities. PyTRiP provides Python bindings and a platform-independent graphical user interface (GUI) for the heavy ion treatment program TRiP, and adds seamless support of DICOM files. We aim to provide a front-end for TRiP which does not require any special computer skills. Methods: PyTRiP is written in Python combined with C for fast computing. Routines for DICOM file import/export to TRiPs native file format are implemented. The GUI comes as an executable with all its dependencies including PyTRiP making it easy to install on Windows, Mac and Linux. Results: PyTRiP is a comprehensive toolbox for handling TRiP. Treatment plans are handled using an object oriented structure. Bindings to TRiP (which only runs on Linux, either locally or on a remote server) are performed through a single function call. GUI users can intuitively create treatment plans without much knowledge about the TRiP user interface. Advanced users still have full access to all TRiP functionality. The user interface comes with a comprehensive plotting tool, which can visualize 2D contours, volume histograms, as well as dose- and linear energy transfer (LET) distributions. Conclusion: We developed a powerful toolbox for ion therapy research using TRiP as backend. The corresponding GUI allows to easily and intuitively create, calculate and visualize treatment plans. TRiP is thereby more accessible and simpler to use.

Inventory of greenhouse gases emissions from gasoline and diesel ...

African Journals Online (AJOL)

Emissions from fossil fuel combustion are of global concern due to their negative effects on public health and environment. This paper is an inventory of the greenhouse gases (GHGs) released into the environment through consumption of fuels (gasoline and diesel) in Nigeria from 1980 to 2014. The fuel consumption data ...

Hydrogen isotope inventory in the graphite divertor tiles of ASDEX Upgrade as measured by thermal desorption spectroscopy

International Nuclear Information System (INIS)

Franzen, P.; Behrisch, R.; Garcia-Rosales, C.; Schleussner, D.; Roesler, D.; Becker, J.; Knapp, W.; Edelmann, C.

1997-01-01

The hydrogen and deuterium inventories of the ASDEX Upgrade divertor tiles were measured after the experimental period from December 1994 to July 1995 by thermal desorption spectroscopy (TDS) of samples cut out of the divertor tiles. The samples were heated by electron bombardment up to 2100 K; the released gases were measured by means of a calibrated quadrupole mass spectrometer. The measured hydrogen or deuterium inventories are of the order of 10 23 m -2 . They are larger for samples of the inner divertor than of the outer divertor by a factor of about 2. The largest inventory was found at the separatrix position of the inner divertor. Most of the released hydrogen (H) can be attributed to water adsorbed in the near surface region during the air exposure prior to the TDS measurements. The total inventories measured by TDS exceed the inventories in the near surface region (< 25 μm) measured by ion beam analysis methods by a factor of up to 10. Hence, the total hydrogen retention is governed by the diffusion out of the near surface region deep into the material. The hydrogen and deuterium inventories decreased with increasing surface temperature. (author). 64 refs, 12 figs, 2 tabs

Control decisions for 3H, 14C, 85Kr, and 129I released from the commercial fuel cycle

International Nuclear Information System (INIS)

Thomas, T.R.; Brown, R.A.

1985-01-01

The effects of complete release of 3 H, 14 C, 85 Kr and 129 I from operating a 400-GWe fuel cycle for 100 years are shown. The postulated accrued health effects (HE) from 14 C and 129 I appear large; however, these numbers are insignificant when compared to the 176 billion cancer deaths that would occur from all causes in the 10,000-year reference period. The percent increase in global cancer deaths would be no greater than 5 x 10 -5 % for each of the radionuclides. Based on the 1980 inventory of each radionuclide in the environment, complete release for 100 years from a 400-GWe fuel cycle would not increase the 3 H or 14 C inventories, however, large increases in 85 Kr and 129 I inventories would occur. The effects, besides dose impacts, of large increases in inventory are unknown and serve only as warning flags that should be taken into consideration. Only 129 I releases from a fuel reprocessing plant would exceed the allowable maximum exposed individual dose limit and 85 Kr and 129 I would exceed the allowable release limit. The effects of controlled releases from commercial fuel reprocessing plants serving a 400-GWe fuel cycle for 100 years are also shown

Tellurium release and deposition during the TMI-2 accident

International Nuclear Information System (INIS)

Vinjamuri, K.; Osetek, D.J.; Hobbins, R.R.; Jessup, J.S.

1984-09-01

The estimated behavior of tellurium during and after the accident at the Three Mile Island Unit-2 is presented. The behavior is based on all available measurement data for /sup 129m/Te, 132 Te, stable tellurium ( 126 Te, 128 Te and 130 Te), and best estimate calculations of tellurium release and transport. The predicted release was calculated using current techniques that relate release rate to fuel temperature and holdup of tellurium in zircaloy until significant oxidation occurs. The calculated release fraction was low, approx. 7%, but the total measured release for samples analyzed to date is about 5.8%. Of the measured tellurium about 2.4, 1.8, 0.88, 0.42, 0.17 and 0.086% of core inventory were in the containment sump water, upper plenum assembly surfaces, containment solids in the sump water, makeup and purification demineralizer, containment inside surface, and the reactor primary coolant, respectively. A significant fraction (54%) of the tellurium calculated to be retained on the upper plenum surfaces (4.61% of the core inventory) was deposited during the high pressure injection of coolant at about 200 min after the reactor scram. Comparison of tellurium behavior with in-pile and out-of-pile tests strongly suggests that zircaloy holds tellurium until significant cladding oxidation occurs

The total release of xenon-133 from the Fukushima Dai-ichi nuclear power plant accident

International Nuclear Information System (INIS)

Stohl, Andreas; Seibert, Petra; Wotawa, Gerhard

2012-01-01

The accident at the Fukushima Dai-ichi nuclear power plant (FD-NPP) on 11 March 2011 released large amounts of radioactivity into the atmosphere. We determine the total emission of the noble gas xenon-133 ( 133 Xe) using global atmospheric concentration measurements. For estimating the emissions, we used three different methods: (i) using a purely observation-based multi-box model, (ii) comparisons of dispersion model results driven with GFS meteorological data with the observation data, and (iii) such comparisons with the dispersion model driven by ECMWF data. From these three methods, we have obtained total 133 Xe releases from FD-NPP of (i) 16.7 ± 1.9 EBq, (ii) 14.2 ± 0.8 EBq, and (iii) 19.0 ± 3.4 EBq, respectively. These values are substantially larger than the entire 133 Xe inventory of FD-NPP of about 12.2 EBq derived from calculations of nuclear fuel burn-up. Complete release of the entire 133 Xe inventory of FD-NPP and additional release of 133 Xe due to the decay of iodine-133 ( 133 I), which can add another 2 EBq to the 133 Xe FD-NPP inventory, is required to explain the atmospheric observations. Two of our three methods indicate even higher emissions, but this may not be a robust finding given the differences between our estimates. - Highlights: ► We determine the total release of xenon-133 from the Fukushima nuclear accident. ► We used global measurements and a box model, as well as dispersion model estimates. ► Total 133 Xe release is about 14.2-19 EBq, more than Fukushima 133 Xe inventory. ► Additional release of iodine-133 and decay into 133 Xe needed to explain results.

Radioactive releases into the environment under accidental conditions

International Nuclear Information System (INIS)

Beninson, D.

1976-01-01

Although accidents involving the release of radioactive materials and the unplanned exposure of people can occur at any stage of the nuclear fuel cycle, most attention has been focused on reactor accidents. Although no power reactor accidents involving exposure of the public have yet occured, it should be recognized that the probability of such accidental releases cannot be reduced to zero. Since the inventory of radioactive materials in power reactors is very large, it is usual to postulate, for safety assessments, that a release of fission products takes place in spite of all protective measures. This postulated release is of importance for reactor siting and for preparing emergency plans. (HP) [de

54Mn release from LMFBR cores

International Nuclear Information System (INIS)

Polley, M.V.

1976-10-01

The inventory of 54 Mn per unit exposed area of stainless steel in LMFBR cores may be calculated using a formula originally derived at HEDL. This treats the simultaneous production by activation and release by corrosion and diffusion of 54 Mn and assumes that the concentration at the steel surface is zero. The inventory per unit exposed area is calculated as a function of temperature and is compared with that calculated simply by assuming stoichiometric corrosion. An effective diffusion coefficient is used in the calculations which include contributions from both lattice and grain boundary diffusion. A general relationship is derived for the effective diffusion coefficient and it is shown how values may be obtained using the Levine-MacCallum and the Fisher theories of grain boundary diffusion. Values of the lattice diffusion coefficient were obtained by analysing data obtained from sodium loop experiments. The effect on the inventory due to the possible formation of a ferrite layers on the exposed surface is discussed and it is also shown how the inventory over several fuel cycles may be calculated. (U.K.)

Effect of surface water on tritium release behavior from Li4SiO4

International Nuclear Information System (INIS)

Hanada, T.; Fukada, S.; Nishikawa, M.; Suematsu, K.; Yamashita, N.; Kanazawa, T.

2010-01-01

The tritium release model to represent the release behavior of bred tritium from solid breeder materials has been developed by the blanket group of Kyushu University. It has been found that water is released to the purge gas from solid breeder materials and that this water affects the tritium release behavior. In this study, the amount of surface water released from Li 4 SiO 4 is quantified by the experiment. In addition, the tritium release behavior from Li 4 SiO 4 are estimated based on the tritium release model using parameters obtained in our studies under conditions of commercial reactor operation and ITER test blanket module operation. The effect of the surface water on tritium release behavior is discussed from the obtained results. Moreover, the tritium inventory of Li 4 SiO 4 is discussed based on calculation under the unsteady state condition. Further, the effects of grain size and temperature on distribution of tritium inventory under the steady state condition are evaluated, and the optimal grain size is discussed from the view point of tritium release from Li 4 SiO 4 .

Inventory Control System by Using Vendor Managed Inventory (VMI)

Science.gov (United States)

Sabila, Alzena Dona; Mustafid; Suryono

2018-02-01

The inventory control system has a strategic role for the business in managing inventory operations. Management of conventional inventory creates problems in the stock of goods that often runs into vacancies and excess goods at the retail level. This study aims to build inventory control system that can maintain the stability of goods availability at the retail level. The implementation of Vendor Managed Inventory (VMI) method on inventory control system provides transparency of sales data and inventory of goods at retailer level to supplier. Inventory control is performed by calculating safety stock and reorder point of goods based on sales data received by the system. Rule-based reasoning is provided on the system to facilitate the monitoring of inventory status information, thereby helping the process of inventory updates appropriately. Utilization of SMS technology is also considered as a medium of collecting sales data in real-time due to the ease of use. The results of this study indicate that inventory control using VMI ensures the availability of goods ± 70% and can reduce the accumulation of goods ± 30% at the retail level.

Clinical and histopathological study of the TriPollar home-use device for body treatments.

Science.gov (United States)

Boisnic, Sylvie; Branchet, Marie-Christine; Birnstiel, Oliver; Beilin, Ghislaine

2010-01-01

Professional non invasive treatments for body contouring based on radiofrequency (RF) became popular in aesthetic clinics due to proven efficacy and safety. A new home-use RF device for body treatments has been developed based on TriPollar technology. Our objective was to evaluate the TriPollar home-use device for circumference reduction, cellulite improvement and skin tightening using objective and subjective methods. An ex-vivo human skin model was used for histological and biochemical evaluations of the TriPollar clinical effect. Additionally, twenty four subjects used the new device on the abdomen and thigh areas and the circumference reduction was measured. Ex-vivo models indicated a significant increase of 82% in hypodermal glycerol release. Histology revealed a 34% alteration in adipocyte appearance. Collagen synthesis increased by 31% following TriPollar treatment. A significant average reduction of 2.4 cm was measured on the treated thighs. On the control thighs a lesser, non-significant reduction was found. Average abdominal laxity was reduced from 1.4 at baseline to 0.8 following treatments. A certain reduction was measured in the abdomen circumferences, although it was not significant. The reported results demonstrate the safety and efficacy of the new TriPollar home-use device for body contouring and skin tightening. Treatment may lead to discrete circumference reduction and moderate laxity improvement.

An Integer Programming Model for Multi-Echelon Supply Chain Decision Problem Considering Inventories

Science.gov (United States)

Harahap, Amin; Mawengkang, Herman; Siswadi; Effendi, Syahril

2018-01-01

In this paper we address a problem that is of significance to the industry, namely the optimal decision of a multi-echelon supply chain and the associated inventory systems. By using the guaranteed service approach to model the multi-echelon inventory system, we develop a mixed integer; programming model to simultaneously optimize the transportation, inventory and network structure of a multi-echelon supply chain. To solve the model we develop a direct search approach using a strategy of releasing nonbasic variables from their bounds, combined with the “active constraint” method. This strategy is used to force the appropriate non-integer basic variables to move to their neighbourhood integer points.

Cost of umbilical cord blood units released for transplantation.

Science.gov (United States)

Sirchia, G; Rebulla, P; Tibaldi, S; Lecchi, L

1999-06-01

A large number of institutions have started programs banking umbilical cord blood (UCB) for allogeneic unrelated-donor and related-donor transplantation. However, limited information is available on the financial issues surrounding these activities. The aim of this study was to determine the fee per UCB unit released for transplantation that would allow cost recovery after 10 years. Three organizational models were considered suitable to provide units for five UCB transplants per 1 million population per year, a figure that would translate into an annual need for 280 units in Italy. Models A, B, and C included, respectively, seven networked banks, each with an inventory of 1,500 units; two networked banks, each with an inventory of 5,000 units; and one bank with an inventory of 10,000 units. It was estimated that it would take 3 years to develop the cryopreserved inventory and that approximately 3 percent of the inventory could be released and replaced each year during the 7-year interval between the fourth and tenth years of activity. The data on the costs of labor, reagents and diagnostics, disposables, depreciation and maintenance, laboratory tests, and overhead, as well as the operational data used in the analysis were collected at the Milano Cord Blood Bank in 1996. Fees of US $15,061, $12,666, and $11,602 per unit released during the fourth through the tenth years of activity allow full cost recovery (principle and interest) under Models A, B, and C, respectively. Although UCB procurement costs compare favorably with those of other hematopoietic cell sources, these results and the current fee of US $15,300 used in some institutions show that UCB is an expensive resource. Therefore, judicious planning of banking programs with high quality standards is necessary to prevent economic losses. The advantages of lower fees associated with the centralized banking approach of Model C should be balanced with the more flexible collection offered by Model A.

ADHD: Tips to Try

Science.gov (United States)

... Staying Safe Videos for Educators Search English Español ADHD: Tips to Try KidsHealth / For Teens / ADHD: Tips to Try Print en español TDAH: Consejos que puedes probar ADHD , short for attention deficit hyperactivity disorder , is a ...

Transient fission product release during reactor shutdown and startup

International Nuclear Information System (INIS)

Hunt, C.E.L.; Lewis, B.J.

1995-01-01

Sweep gas experiments performed at CRL from 1979 to 1985 have been analysed to determine the fraction of the fission product gas inventory that is released on reactor shutdown and startup. Empirical equations were derived and applied to calculate the xenon release from companion fuel elements and from a well documented experimental fuel bundle irradiated in the NRU reactor. The measured gas release could be matched to within about a factor of two for an experimental irradiation with a burnup of 217 MWh/kgU. (author)

Geometric Programming Approach to an Interactive Fuzzy Inventory Problem

Directory of Open Access Journals (Sweden)

Nirmal Kumar Mandal

2011-01-01

Full Text Available An interactive multiobjective fuzzy inventory problem with two resource constraints is presented in this paper. The cost parameters and index parameters, the storage space, the budgetary cost, and the objective and constraint goals are imprecise in nature. These parameters and objective goals are quantified by linear/nonlinear membership functions. A compromise solution is obtained by geometric programming method. If the decision maker is not satisfied with this result, he/she may try to update the current solution to his/her satisfactory solution. In this way we implement man-machine interactive procedure to solve the problem through geometric programming method.

Inventory Control System by Using Vendor Managed Inventory (VMI

Directory of Open Access Journals (Sweden)

Dona Sabila Alzena

2018-01-01

Full Text Available The inventory control system has a strategic role for the business in managing inventory operations. Management of conventional inventory creates problems in the stock of goods that often runs into vacancies and excess goods at the retail level. This study aims to build inventory control system that can maintain the stability of goods availability at the retail level. The implementation of Vendor Managed Inventory (VMI method on inventory control system provides transparency of sales data and inventory of goods at retailer level to supplier. Inventory control is performed by calculating safety stock and reorder point of goods based on sales data received by the system. Rule-based reasoning is provided on the system to facilitate the monitoring of inventory status information, thereby helping the process of inventory updates appropriately. Utilization of SMS technology is also considered as a medium of collecting sales data in real-time due to the ease of use. The results of this study indicate that inventory control using VMI ensures the availability of goods ± 70% and can reduce the accumulation of goods ± 30% at the retail level.

Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU fuel

International Nuclear Information System (INIS)

Tait, J.C.; Gauld, I.; Kerr, A.H.

1995-01-01

The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and fission-product inventories calculated using the ORIGEN-S code coupled with the WIMS-AECL lattice code, using data from analytical measurements of radioisotope inventories in Pickering CANDU reactor fuel. The recent processing of new ENDF/B-VI cross-section data has allowed the ORIGEN-S calculations to be performed using the most up-to-date nuclear data available. The results indicate that the code is reliably predicting actinide and the majority of fission-product inventories to within the analytical uncertainty. ((orig.))

Inventory Control System by Using Vendor Managed Inventory (VMI)

OpenAIRE

Dona Sabila Alzena; Mustafid Mustafid; Suryono Suryono

2018-01-01

The inventory control system has a strategic role for the business in managing inventory operations. Management of conventional inventory creates problems in the stock of goods that often runs into vacancies and excess goods at the retail level. This study aims to build inventory control system that can maintain the stability of goods availability at the retail level. The implementation of Vendor Managed Inventory (VMI) method on inventory control system provides transparency of sales data an...

76 FR 7841 - Agency Information Collection Activities; Proposed Collections; Toxic Chemical Release Reporting...

Science.gov (United States)

2011-02-11

... agencies, and others to promote reductions in toxic chemical releases. Industrial facilities use the TRI... Activities; Proposed Collections; Toxic Chemical Release Reporting; Request for Comments on Proposed Renewal... the individual listed in the preceding FOR FURTHER INFORMATION CONTACT section. Title: Toxic Chemical...

Purchasing and inventory management techniques for optimizing inventory investment

International Nuclear Information System (INIS)

McFarlane, I.; Gehshan, T.

1993-01-01

In an effort to reduce operations and maintenance costs among nuclear plants, many utilities are taking a closer look at their inventory investment. Various approaches for inventory reduction have been used and discussed, but these approaches are often limited to an inventory management perspective. Interaction with purchasing and planning personnel to reduce inventory investment is a necessity in utility efforts to become more cost competitive. This paper addresses the activities that purchasing and inventory management personnel should conduct in an effort to optimize inventory investment while maintaining service-level goals. Other functions within a materials management organization, such as the warehousing and investment recovery functions, can contribute to optimizing inventory investment. However, these are not addressed in this paper because their contributions often come after inventory management and purchasing decisions have been made

Measurement of gap and grain-boundary inventories of 129I in used CANDU fuels

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.; Moir, D.L.; Kolar, M.; Porth, R.J.; McConnell, J.L.; Kerr, A.H.

1995-01-01

Combined gap and grain-boundary inventories of 129 I in 14 used CANDU fuel elements were measured by crushing and simultaneously leaching fuel segments for 4 h in a solution containing KI carrier. From analogy with previous work a near one-to-one correlation was anticipated between the amount of stable Xe and the amount of 128 I in the combined gap and grain-boundary regions of the fuel. However, the results showed that such a correlation was only apparent for low linear power rating (LLPR) fuels with an average linear power rating of 44 kW/m), the 129 I values were considerably smaller than expected. The combined gap and grain-boundary inventories of 129 I in the 14 fuels tested varied from 1.8 to 11.0%, with an average value of 3.6 ± 2.4% which suggests that the average value of 8.1 ± 1% used in safety assessment calculations overestimates the instant release fraction for 129 I. Segments of used CANDU fuels were leached for 92 d (samples taken at 5, 28 and 92 d) to determine the kinetics of 129 I release. Results could be fitted tentatively to half-order reaction kinetics, implying that 129 I release is a diffusion-controlled process for LLPR fuels, and also for HLPR fuels, once the gap inventory has been leached. However, more data are needed over longer leaching periods to gain more understanding of the processes that control grain-boundary release of 129 I from used CANDU fuel

Optimization of Inventory

OpenAIRE

PROKOPOVÁ, Nikola

2017-01-01

The subject of this thesis is optimization of inventory in selected organization. Inventory optimization is a very important topic in each organization because it reduces storage costs. At the beginning the inventory theory is presented. It shows the meaning and types of inventory, inventory control and also different methods and models of inventory control. Inventory optimization in the enterprise can be reached by using models of inventory control. In the second part the company on which is...

A user's guide to the reactor inventory module NECTAR-RICE

International Nuclear Information System (INIS)

Barker, C.D.

1982-01-01

The NECTAR environmental computer code has been developed to meet the increasing demand for comprehensive calculations of the radiological consequences of the atmosphere release of radionuclides from a nuclear facility. The code consists of a main control program, library listing/modification routines and five calculational modules. The input data required for the reactor inventory module NECTAR-RICE is described. This data includes facilities for specifying the initial conditions, controlling the irradiation conditions of the fuel and for temporarily modifying library data at different stages of the calculation. The structure of the module is briefly described and three sample cases are given to facilitate understanding of the program's use and program testing. These sample cases demonstrate the three different ways of running the program, namely to calculate actinide inventories only, fission product inventories only or to do a composite actinide and fission product calculation. (author)

Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU Fuel

International Nuclear Information System (INIS)

Tait, J.C.; Gauld, I.; Kerr, A.H.

1994-10-01

The safety assessment being conducted by AECL Research for the concept of deep geological disposal of used CANDU UO 2 fuel requires the calculation of radionuclide inventories in the fuel to provide source terms for radionuclide release. This report discusses the validation of selected actinide and fission-product inventories calculated using the ORIGEN-S code coupled with the WIMS-AECL lattice code, using data from analytical measurements of radioisotope inventories in Pickering CANDU reactor fuel. The recent processing of new ENDF/B-VI cross-section data has allowed the ORIGEN-S calculations to be performed using the most up-to-date nuclear data available. The results indicate that the code is reliably predicting actinide and the majority of fission-product inventories to within the analytical uncertainty. 38 refs., 4 figs., 5 tabs

Joint inventory control and pricing in a service-inventory system

DEFF Research Database (Denmark)

Marand, Ata Jalili; Li, Hongyan Jenny; Thorstenson, Anders

2017-01-01

This study addresses joint inventory control and pricing decisions for a service-inventory system. In such a system both an on-hand inventory item and a positive service time are required to fulfill customer demands. The service-inventory system also captures main features of the classical...... inventory systems with a positive processing time, e.g., make-to-order systems. In this study, the service-inventory system is modeled as an M/M/1 queue in which the customer arrival rate is price dependent. The inventory of an individual item is continuously reviewed under an (r,Q) policy....... The replenishment lead times of the inventory are exponentially distributed. Furthermore, customers arriving during stock-out periods are lost. The stochastic customer inter-arrival times, service times, and inventory replenishment lead times cause the high complexity of the problem and the difficulty in solving it...

Tritium inventory measurements using calorimetry

International Nuclear Information System (INIS)

Kapulla, H.; Kraemer, R.; Heine, R.

1992-01-01

In the past calorimetry has been developed as a powerful tool in radiometrology. Calorimetric methods have been applied for the determination of activities, half lives and mean energies released during the disintegration of radioactive isotopes. The fundamental factors and relations which determine the power output of radioactive samples are presented and some basic calorimeter principles are discussed in this paper. At the Kernforschungszentrum Karlsruhe (KfK) a family of 3 calorimeters has been developed to measure the energy release from radiative waste products arising from reprocessing operations. With these calorimeters, radiative samples with sizes from a few cm 3 to 2 ·10 5 cm 3 and heat ratings ranging from a few nW to kW can be measured. After modifications of tits inner part the most sensitive calorimeter among the three calorimeters mentioned above would be best suited for measuring the tritium inventory in T-getters of the Amersham-type

76 FR 2677 - Request Facilities To Report Toxics Release Inventory Information Electronically or Complete Fill...

Science.gov (United States)

2011-01-14

... reflected by the generally increasing percentage of facilities that submit TRI reporting forms... ability to submit valid chemical data files from third party software using eXtensible Markup Language...

Calculations in support of a potential definition of large release

International Nuclear Information System (INIS)

Hanson, A.L.; Davis, R.E.; Mubayi, V.

1994-05-01

The Nuclear Regulatory Commission has stated a hierarchy of safety goals with the qualitative safety goals as Level I of the hierarchy, backed up by the quantitative health objectives as Level II and the large release guideline as Level III. The large release guideline has been stated in qualitative terms as a magnitude of release of the core inventory whose frequency should not exceed 10 -6 per reactor year. However, the Commission did not provide a quantitative specification of a large release. This report describes various specifications of a large release and focuses, in particular, on an examination of releases which have a potential to lead to one prompt fatality in the mean. The basic information required to set up the calculations was derived from the simplified source terms which were obtained from approximations of the NUREG-1150 source terms. Since the calculation of consequences is affected by a large number of assumptions, a generic site with a (conservatively determined) population density and meteorology was specified. At this site, various emergency responses (including no response) were assumed based on information derived from earlier studies. For each of the emergency response assumptions, a set of calculations were performed with the simplified source terms; these included adjustments to the source terms, such as the timing of the release, the core inventory, and the release fractions of different radionuclides, to arrive at a result of one mean prompt fatality in each case. Each of the source terms, so defined, has the potential to be a candidate for a large release. The calculations show that there are many possible candidate source terms for a large release depending on the characteristics which are felt to be important

Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

International Nuclear Information System (INIS)

Minato, Kazuo; Sawa, Kazuhiro; Koya, Toshio; Tomita, Takeshi; Ishikawa, Akiyoshi; Baldwin, Charles A.; Gabbard, William Alexander; Malone, Charlie M.

2000-01-01

Postirradiation heating tests of TRISO-coated UO 2 particles at 1700 and 1800degC were performed to understand fission product release behavior at accident temperatures. The inventory measurements of the individual particles were carried out before and after the heating tests with gamma-ray spectrometry to study the behavior of the individual particles. The time-dependent release behavior of 85 Kr, 110m Ag, 134 Cs, 137 Cs, and 154 Eu were obtained with on-line measurements of fission gas release and intermittent measurements of metallic fission product release during the heating tests. The inventory measurements of the individual particles revealed that fission product release behavior of the individual particles was not uniform, and large particle-to-particle variations in the release behavior of 110m Ag, 134 Cs, 137 Cs, and 154 Eu were found. X-ray microradiography and ceramography showed that the variations could not be explained by only the presence or absence of cracks in the SiC coating layer. The SiC degradation may have been related to the variations

Canadian pollutant releases and transfers : NPRI data 1998

International Nuclear Information System (INIS)

2001-03-01

A large, two-sided fold-out poster showing pollution hotspots throughout Canada, has been released by the Canadian Institute for Environmental Law and Policy (CIELAP). The poster is based on the maps and tables of the National Pollutant Release Inventory (NPRI) 1998. It presents the top on-site releases and off-site transfers of pollutants by facilities across Canada, and provides a summary of releases, transfers and recycling of pollutants by province. The map depicts the facilities with the five largest quantities of individual pollutants released to each medium, i. e. water, air, land, underground. The crude oil and gas, other utilities, primary metal, paper and chemical industrial sectors are responsible for the largest on-site releases, while the business services, fabricated metal. primary metal and chemical industrial sectors account for the largest off-site transfers. Twenty-five of the 176 substances whose releases and transfers are reported under the NPRI are classified as 'toxic' or 'carcinogenic'. tabs., maps

LOFC fission product release and circulating activity calculations for gas-cooled reactors

International Nuclear Information System (INIS)

Apperson, C.E. Jr.; Carruthers, L.M.; Lee, C.E.

1977-01-01

The inventories of fission products in a gas-cooled reactor under accident and normal steady state conditions are time and temperature dependent. To obtain a reasonable estimate of these inventories it is necessary to consider fuel failure, a temperature dependent variable, and radioactive decay, a time dependent variable. Using arbitrary radioactive decay chains and published fuel failure models for the High Temperature Gas-Cooled Reactor (HTGR), methods have been developed to evaluate the release of fission products during the Loss of Forced Circulation (LOFC) accident and the circulating and plateout fission product inventories during steady state non-accident operation. The LARC-2 model presented here neglects the time delays in the release from the HTGR due to diffusion of fission products from particles in the fuel rod through the graphite matrix. It also neglects the adsorption and evaporation process of metallics at the fuel rod-graphite and graphite-coolant hole interfaces. Any time delay due to the finite time of transport of fission products by convection through the coolant to the outside of the prestressed concrete reactor vessel (PCRV) is also neglected. This model assumes that all fission products released from fuel particles are immediately deposited outside the PCRV with no time delay

Work in process level definition: a method based on computer simulation and electre tri

Directory of Open Access Journals (Sweden)

Isaac Pergher

2014-09-01

Full Text Available This paper proposes a method for defining the levels of work in progress (WIP in productive environments managed by constant work in process (CONWIP policies. The proposed method combines the approaches of Computer Simulation and Electre TRI to support estimation of the adequate level of WIP and is presented in eighteen steps. The paper also presents an application example, performed on a metalworking company. The research method is based on Computer Simulation, supported by quantitative data analysis. The main contribution of the paper is its provision of a structured way to define inventories according to demand. With this method, the authors hope to contribute to the establishment of better capacity plans in production environments.

ZZ ECN-BUBEBO, ECN-Petten Burnup Benchmark Book, Inventories, Afterheat

International Nuclear Information System (INIS)

Kloosterman, Jan Leen

1999-01-01

Description of program or function: Contains experimental benchmarks which can be used for the validation of burnup code systems and accompanied data libraries. Although the benchmarks presented here are thoroughly described in literature, it is in many cases not straightforward to retrieve unambiguously the correct input data and corresponding results from the benchmark Descriptions. Furthermore, results which can easily be measured, are sometimes difficult to calculate because of conversions to be made. Therefore, emphasis has been put to clarify the input of the benchmarks and to present the benchmark results in such a way that they can easily be calculated and compared. For more thorough Descriptions of the benchmarks themselves, the literature referred to here should be consulted. This benchmark book is divided in 11 chapters/files containing the following in text and tabular form: chapter 1: Introduction; chapter 2: Burnup Credit Criticality Benchmark Phase 1-B; chapter 3: Yankee-Rowe Core V Fuel Inventory Study; chapter 4: H.B. Robinson Unit 2 Fuel Inventory Study; chapter 5: Turkey Point Unit 3 Fuel Inventory Study; chapter 6: Turkey Point Unit 3 Afterheat Power Study; chapter 7: Dickens Benchmark on Fission Product Energy Release of U-235; chapter 8: Dickens Benchmark on Fission Product Energy Release of Pu-239; chapter 9: Yarnell Benchmark on Decay Heat Measurements of U-233; chapter 10: Yarnell Benchmark on Decay Heat Measurements of U-235; chapter 11: Yarnell Benchmark on Decay Heat Measurements of Pu-239

A novel tri-layer flexible piezoelectric nanogenerator based on surface- modified graphene and PVDF-BaTiO3 nanocomposites

Science.gov (United States)

Yaqoob, Usman; Uddin, A. S. M. Iftekhar; Chung, Gwiy-Sang

2017-05-01

The fabrication and characterization of a novel tri-layer piezoelectric nanogenerator (PNG) based on poly(vinylidene fluoride) (PVDF), barium titanate (BTO), and surface-modified n- type graphene (n-Gr) have been investigated. The n-Gr, with its majority of negative charge carriers, plays a vital role in enhancing the energy-harvesting performance by aligning the dipoles in one direction. The tri-layer structure obtains by stacking two layers of PVDF-BTO nanocomposite films, one on each side of the n-Gr layer. The fabricated tri-layer PNG shows a maximum output voltage of 10 V (pk-pk) along with a current of 2.5 μA (pk-pk) at an applied force of 2 N. Furthermore, the PNG Exhibits 5.8 μW instantaneous power at 1 MΩ load resistance. Moreover, the fabricated device demonstrated good stability even after 1000 pressing-releasing cycles. This novel tri-layer PNG structure can opens a promising avenue for future piezoelectric generating technologies.

Ex vivo human skin evaluation of localized fat reduction and anti-aging effect by TriPollar radio frequency treatments.

Science.gov (United States)

Boisnic, Sylvie; Branchet, Marie Christine

2010-02-01

A wide variety of radio frequency (RF) treatments for localized fat and cellulite reduction as well as anti-aging are available nowadays, but only a few have shown the biological mechanism responsible for the clinical results. To determine the biological mechanism of the TriPollar RF device for localized fat and cellulite reduction as well as the collagen remodeling effect. Human skin samples were collected from abdominoplasty surgery and facial lifts, in order to evaluate the lipolytic and anti-aging effects of the apollo device powered by TriPollar RF technology using an ex vivo human skin model. The anti-cellulite effect was evaluated by the dosage of released glycerol and histological analysis of the hypodermis. Skin tightening was evaluated by morphometric analysis of collagen fibers and the dosage of collagen synthesis. Following TriPollar treatment, a significant increase of glycerol release by skin samples was found. The structure of fat cells was altered in shape and a modification of the fibrous tract was also detected in the fat layer. Additional findings indicated stimulation of the dermal fibroblasts with increased collagen synthesis. The detected alteration in the hypodermal layer is manifested by fat and cellulite reduction accompanied by structural and biochemical improvement of dermal collagen, which result in overall skin tightening.

Derivation of a radionuclide inventory for irradiated graphite-chlorine-36 inventory determination

International Nuclear Information System (INIS)

Brown, F.J.; Palmer, J.D.; Wood, P.

2001-01-01

fraction of the chlorine is released from the graphite during irradiation, both in natural precursor and activated form. The release rate of inactive chlorine and of chlorine-36 was modelled, to allow the calculation of a residual chlorine-36 inventory in operational and decommissioning wastes; actual measurements on operational wastes have confirmed this release. This has subsequently been used to assess the effect on disposal risks. This paper provides a description of the work undertaken by Nirex to establish the residual inventory of chlorine-36 in irradiated nuclear graphite, and outline the implications for disposal of these wastes. (author)

Tri-generation nation

International Nuclear Information System (INIS)

Pichon, Max

2010-01-01

Full text: Sydney and Melbourne councils are looking to outperform each other with ambitious greenhouse and energy efficiency initiatives. Sydney wants to cut CO_2 by 70 per cent by 2030, while Melbourne's 1200 Buildings retrofit project speaks for itself. One key technology both councils are tapping is trigeneration, which generates electricity, heating and cooling from local gas-fired power units. From a physics perspective, a combustion process cannot be more than 30 per cent efficient, so capturing and using the waste heat can lead to great savings. Sydney Lord Mayor Clover Moore said a third of the council's carbon reduction goal of 3.9Mt a year by 2030 will come from tri-gen. Melbourne is aiming to achieve zero net emissions by 2020, which means eliminating 5.8Mt of CO_2, a lot of it through tri-gen. It has already seen a surge among landlords. GPT, Stockland and Mirvac have all stuck tri-gen units in Sydney office developments, while newly carbon- neutral NAB has installed the technology on its data centre in Melbourne and expects to save 20,000 tonnes of CO_2 a year. But one expert, while welcoming the spike in popularity, says there are traps for the unwary. Johnson Controls' Peter Moser sees two core drivers for its uptake. “First is the prominence of GreenStar and NABERS. Many companies will move to tri-gen as they will want the extra points or stars,” he told WME. “Secondly, there is the continuous increase in the price of energy. At the same time there may be an [emissions trading scheme] or a carbon price introduced, and that puts pressure on the consumer. Combining those two scenarios will see more people adopt tri-gen because it will become more economically viable and the payback periods of tri-gen will come down considerably.” But he points to the importance of pre-planning when considering tri-gen, warning. “To put tri-gen into a building, let alone retrofit a whole city and make it work, you need highly complex teams working together

Assessment of the dose to a representative Japanese due to stationary release of tritium to the environment

International Nuclear Information System (INIS)

Saito, Masahiro

2005-01-01

The computer program TriStat was applied to estimate the dose to a representative Japanese due to a stationary release of tritium as HTO and/or HT to the atmosphere from nuclear facilities. In TriStat, the air tritium concentration is estimated by a Gaussian dispersion model. The tritium deposition to the soil was assumed to occur both by dry and wet deposition processes of atmospheric tritium. The primary process of tritium transfer to human body is assumed to take place through a local food-chain in the contaminated area. Tritium concentrations in soil, vegetables and forage were estimated as the tritium concentration per water equivalent. The food chain was modeled by assuming a vegetable compartment and an animal-food compartment. By using TriStat the annual dose to the representative Japanese was evaluated for stationary release of tritium as a function of the distance from a release point. The dose contribution from drinking water was neglected, since the drinking water is generally supplied as tap water or as commercial bottled water. In the case of HT release, the committed dose due to tritium intake through breathing and skin absorption was found to be of minor importance. (author)

The release of fission products from uranium metal: a review

International Nuclear Information System (INIS)

Minshall, P.C.

1989-03-01

The literature on the release of fission products as gaseous species from irradiated uranium metal in oxidising atmospheres has been reviewed. Release of actinides and of fission products as spalled particulate were not considered. Data is given on the release in air, carbon dioxide, steam and mixtures of steam and air. The majority of data discussed lie between 800 and 1200 0 C though some results for xenon, krypton and iodine releases below 800 0 C are given. Two measures of fission product release are discussed: the release fraction, F(tot), which is the ratio of the total release to the initial inventory, and the fractional release, F(ox), which is the fraction released from the oxidised metal. The effect of burn-up, atmosphere and temperature on F(tot) and F(ox) is examined and the conditions under which the release fraction, F(tot) is proportional to the extent of oxidation discussed. (author)

Applying inventory classification to a large inventory management system

Directory of Open Access Journals (Sweden)

Benjamin Isaac May

2017-06-01

Full Text Available Inventory classification aims to ensure that business-driving inventory items are efficiently managed in spite of constrained resources. There are numerous single- and multiple-criteria approaches to it. Our objective is to improve resource allocation to focus on items that can lead to high equipment availability. This concern is typical of many service industries such as military logistics, airlines, amusement parks and public works. Our study tests several inventory prioritization techniques and finds that a modified multi-criterion weighted non-linear optimization (WNO technique is a powerful approach for classifying inventory, outperforming traditional techniques of inventory prioritization such as ABC analysis in a variety of performance objectives.

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Science.gov (United States)

González-Robles, E.; Serrano-Purroy, D.; Sureda, R.; Casas, I.; de Pablo, J.

2015-10-01

The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, and the grain boundaries and, if present, in the high burn-up structure (HBS). The values calculated from this theoretical approach correspond to an upper limit that likely does not correspond to what it will be expected to be instantaneously released in the real system. Trying to ascertain this IRF from an experimental point of view, static leaching experiments have been carried out with two commercial UO2 spent nuclear fuels (SNF): one from a pressurized water reactor (PWR), labelled PWR, with an average burn-up (BU) of 52 MWd/kgU and fission gas release (FGR) of 23.1%, and one from a boiling water reactor (BWR), labelled BWR, with an average BU of and 53 MWd/kgU and FGR of 3.9%. One sample of each SNF, consisting of fuel and cladding, has been leached in bicarbonate water during one year under oxidizing conditions at room temperature (25 ± 5)°C. The behaviour of the concentration measured in solution can be divided in two according to the release rate. All radionuclides presented an initial release rate that after some days levels down to a slower second one, which remains constant until the end of the experiment. Cumulative fraction of inventory in aqueous phase (FIAPc) values has been calculated. Results show faster release in the case of the PWR SNF. In both cases Np, Pu, Am, Cm, Y, Tc, La and Nd dissolve congruently with U, while dissolution of Zr, Ru and Rh is slower. Rb, Sr, Cs and Mo, dissolve faster than U. The IRF of Cs at 10 and 200 days has been calculated, being (3.10 ± 0.62) and (3.66 ± 0.73) for PWR fuel, and (0.35 ± 0.07) and (0.51 ± 0.10) for BWR fuel.

Fission Product Release from Spent Nuclear Fuel During Melting

International Nuclear Information System (INIS)

Howell, J.P.; Zino, J.F.

1998-09-01

The Melt-Dilute process consolidates aluminum-clad spent nuclear fuel by melting the fuel assemblies and diluting the 235U content with depleted uranium to lower the enrichment. During the process, radioactive fission products whose boiling points are near the proposed 850 degrees C melting temperature can be released. This paper presents a review of fission product release data from uranium-aluminum alloy fuel developed from Severe Accident studies. In addition, scoping calculations using the ORIGEN-S computer code were made to estimate the radioactive inventories in typical research reactor fuel as a function of burnup, initial enrichment, and reactor operating history and shutdown time.Ten elements were identified from the inventory with boiling points below or near the 850 degrees C reference melting temperature. The isotopes 137Cs and 85Kr were considered most important. This review serves as basic data to the design and development of a furnace off-gas system for containment of the volatile species

Transient fission-product release during reactor shutdown and startup

International Nuclear Information System (INIS)

Hunt, C.E.L.; Lewis, B.J.; Dickson, L.W.

1997-12-01

Sweep-gas experiments performed at AECL's Chalk River Laboratories from 1979 to 1985 have been further analysed to determine the fraction of the gaseous fission-product inventory that is released on reactor shutdown and startup. Empirical equations were derived and applied to calculate the stable xenon release from companion fuel elements and from a well-documented experimental fuel bundle irradiated in the NRU reactor. The calculated gas release could be matched to the measured values within about a factor of two for an experimental irradiation with a burnup of 217 MWh/kgU. There was also limited information on the fraction of the radioactive iodine that was exposed, but not released, on reactor shutdown. An empirical equation is proposed for calculating this fraction. (author)

Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Minato, Kazuo [Japan Atomic Energy Research Institute (Japan); Sawa, Kazuhiro [Japan Atomic Energy Research Institute (Japan); Koya, Toshio [Japan Atomic Energy Research Institute (Japan); Tomita, Takeshi [Japan Atomic Energy Research Institute (Japan); Ishikawa, Akiyoshi [Japan Atomic Energy Research Institute (Japan); Baldwin, Charles A; Gabbard, William Alexander [Oak Ridge National Laboratory (United States); Malone, Charlie M [Oak Ridge National Laboratory (United States)

2000-07-15

Postirradiation heating tests of TRISO-coated UO{sub 2} particles at 1700 and 1800degC were performed to understand fission product release behavior at accident temperatures. The inventory measurements of the individual particles were carried out before and after the heating tests with gamma-ray spectrometry to study the behavior of the individual particles. The time-dependent release behavior of {sup 85}Kr, {sup 110m}Ag, {sup 134}Cs, {sup 137}Cs, and {sup 154}Eu were obtained with on-line measurements of fission gas release and intermittent measurements of metallic fission product release during the heating tests. The inventory measurements of the individual particles revealed that fission product release behavior of the individual particles was not uniform, and large particle-to-particle variations in the release behavior of {sup 110m}Ag, {sup 134}Cs, {sup 137}Cs, and {sup 154}Eu were found. X-ray microradiography and ceramography showed that the variations could not be explained by only the presence or absence of cracks in the SiC coating layer. The SiC degradation may have been related to the variations.

Raw data from the Italian National Forest Inventory are on-line and publicly available

Directory of Open Access Journals (Sweden)

Borghetti M

2016-12-01

Full Text Available Raw data from the Italian National Forest Inventory are on-line and publicly available. The National Forest Service in cooperation with the Forest Monitoring and Management Research Unit of the Council for Agricultural Research and Economics (CREA released the raw data from the National Inventory of Forests and forest Carbon pools - INFC2005 project, the second Italian national forest inventory. Data are available together with metadata information at http://www.inventarioforestale.org/. Users, after registration, can download data from 230.874 living tree stems, 16.472 dead tree stems, 31.083 stumps, from a total of 7.272 field plots (for 1.384 of them additional data on fine woody debris and soil carbon pools are also available.

Estimation of global inventories of radioactive waste and other radioactive materials

International Nuclear Information System (INIS)

2008-06-01

A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

Inventory parameters

CERN Document Server

Sharma, Sanjay

2017-01-01

This book provides a detailed overview of various parameters/factors involved in inventory analysis. It especially focuses on the assessment and modeling of basic inventory parameters, namely demand, procurement cost, cycle time, ordering cost, inventory carrying cost, inventory stock, stock out level, and stock out cost. In the context of economic lot size, it provides equations related to the optimum values. It also discusses why the optimum lot size and optimum total relevant cost are considered to be key decision variables, and uses numerous examples to explain each of these inventory parameters separately. Lastly, it provides detailed information on parameter estimation for different sectors/products. Written in a simple and lucid style, it offers a valuable resource for a broad readership, especially Master of Business Administration (MBA) students.

Assessment of radiological releases to the environment from a fusion reactor power plant

International Nuclear Information System (INIS)

Shank, K.E.; Oakes, T.W.; Easterly, C.E.

1978-05-01

This report summarizes the expected tritium and activation-product inventories and presents an assessment of the potential radiological releases from a fusion reactor power plant, hypothetically located at the Oak Ridge National Laboratory. Routine tritium releases and the resulting dose assessment are discussed. Uncertainties associated with the conversion of tritium gas to tritium oxide and the global tritium cycling are evaluated. The difficulties of estimating releases of activated materials and the subsequent dose commitment are reviewed

Ball-in-ball ZrO2 nanostructure for simultaneous CT imaging and highly efficient synergic microwave ablation and tri-stimuli-responsive chemotherapy of tumors.

Science.gov (United States)

Long, Dan; Niu, Meng; Tan, Longfei; Fu, Changhui; Ren, Xiangling; Xu, Ke; Zhong, Hongshan; Wang, Jingzhuo; Li, Laifeng; Meng, Xianwei

2017-06-29

Combined thermo-chemotherapy displays outstanding synergically therapeutic efficiency when compared with standalone thermotherapy and chemotherapy. Herein, we developed a smart tri-stimuli-responsive drug delivery system involving X@BB-ZrO 2 NPs (X represents loaded IL, DOX, keratin and tetradecanol) based on novel ball-in-ball-structured ZrO 2 nanoparticles (BB-ZrO 2 NPs). The microwave energy conversion efficiency of BB-ZrO 2 NPs was 41.2% higher than that of traditional single-layer NPs due to the cooperative action of self-reflection and spatial confinement effect of the special two-layer hollow nanostructure. The tri-stimuli-responsive controlled release strategy indicate that integrated pH, redox and microwaves in single NPs based on keratin and tetradecanol could effectively enhance the specific controlled release of DOX. The release of DOX was only 8.1% in PBS with pH = 7.2 and GSH = 20 μM. However, the release could reach about 50% at the tumor site (pH = 5.5, GSH = 13 mM) under microwave ablation. The as-made X@BB-ZrO 2 NPs exhibited perfect synergic therapy effect of chemotherapy and microwave ablation both in subcutaneous tumors (H22 tumor-bearing mice) and deep tumors (liver transplantation VX2 tumor-bearing rabbit model). There was no recurrence and death in the X@BB-ZrO 2 + MW group during the therapy of subcutaneous tumors even on the 42 nd day. The growth rates in the deep tumor of the control, MW and X@BB-ZrO 2 + MW groups were 290.1%, 14.1% and -42% 6 days after ablation, respectively. Dual-source CT was used to monitor the metabolism behavior of the as-made BB-ZrO 2 NPs and traditional CT was utilized to monitor the tumor growth in rabbits. Frozen section examination and ICP results indicated the precise control of drug delivery and enhanced cytotoxicity by the tri-stimuli-responsive controlled release strategy. The ball-in-ball ZrO 2 NPs with high microwave energy conversion efficiency were first developed for synergic microwave ablation and

Mammals, Volta Grande Environmental Unity, Triângulo Mineiro, states of Minas Gerais and São Paulo, Southeastern Brazil.

Directory of Open Access Journals (Sweden)

Lessa, G.

2008-01-01

Full Text Available The Volta Grande Environmental Unity represents one of the few remnants of Cerrado protected by areserve in the Triângulo Mineiro region, municipalities of Conceição das Alagoas (19°55' S, 48°23' W andMiguelópolis (20°12' S, 48°03' W, in the states of Minas Gerais and São Paulo, respectively. The mammalian fauna ofthis reserve was inventoried between 2003 and 2004 to generate estimates about taxonomic composition, richness, andabundance of species. A sampling effort of 832 trapping-nights resulted in 24 species recorded. Cumulative curvessuggest that the overall inventory is not complete and that more species are likely to be registered. The majority ofspecies recorded is widespread along the Cerrado, but include some noteworthy records of endangered species, such asthe Giant anteater (Myrmecophaga tridactyla and the Manned wolf (Chrysocyon brachyurus. The record of thearboreal cricetid rodent Oecomys bicolor represents a slight extension of the southeastern limit of its distribution.

Try and try again--qualitative insights into adolescent smoking experimentation and notions of addiction.

Science.gov (United States)

Leavy, Justine; Wood, Lisa; Phillips, Fiona; Rosenberg, Michael

2010-12-01

addiction is a relatively unexplored issue in youth tobacco control. Increasingly, there is recognition of addiction experiences in regular and irregular teenage smokers. Research was undertaken on behalf of the Smarter than Smoking (STS) project to probe young people's reasons for smoking uptake, their attitudes towards the social acceptability of smoking, predictors of continued smoking after trial and understandings and perceptions of addiction. twenty focus groups were conducted to collect qualitative data from young people (n=92) aged 13 to 15 years from metropolitan and regional areas of Western Australia (WA), from a variety of socioeconomic backgrounds, including young Aboriginal and Torres Strait Islander people. of the young people spoken to, 20% smoked regularly, 40% had tried smoking and 40% had never tried. Acceptability and normalcy of trialling smoking was a recurring theme, with little perceived risk of trial leading to regular smoking or becoming addicted. Even non-smokers accepted 'just having a try' in the context of curiosity, life experiences and 'informed choice'. preventing continuation after trial of smoking among young people needs to increase in importance, given the prevailing norms around 'trying it' and individual choice.

Inventory of chemical releases of nuclear installations in the North-Cotentin

International Nuclear Information System (INIS)

2002-05-01

The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

Forest inventory in Myanmar

Energy Technology Data Exchange (ETDEWEB)

Bo, Sit [Forest Resource Div., Forest Department (Myanmar)

1993-10-01

Forest inventory in Myanmar started in 1850s. Up till 1975, Myanmar Forest Department conducted forest inventories covering approximately one forest division every year. The National Forest Survey and Inventory Project funded by UNDP and assisted by FAO commenced in 1981 and the National Forest Management and Inventory project followed in 1986. Up till end March 1993, pre-investment inventory has covered 26.7 million acres, reconnaissance inventory 5.4 million acres and management inventory has carried out in 12 townships

Forest inventory in Myanmar

International Nuclear Information System (INIS)

Sit Bo

1993-01-01

Forest inventory in Myanmar started in 1850s. Up till 1975, Myanmar Forest Department conducted forest inventories covering approximately one forest division every year. The National Forest Survey and Inventory Project funded by UNDP and assisted by FAO commenced in 1981 and the National Forest Management and Inventory project followed in 1986. Up till end March 1993, pre-investment inventory has covered 26.7 million acres, reconnaissance inventory 5.4 million acres and management inventory has carried out in 12 townships

The impact of turn around time in Brazilian Navy inventories

OpenAIRE

Casagrande, Mauricio

2000-01-01

Approved for public release; distribution is unlimited. This thesis analyzes how the operation of helicopters produced and supported by manufacturers in various countries affect Brazilian Navy repairable inventories levels and costs. The research is based on a scenario where the Brazilian Navy operates 68 helicopters, manufactured by contractors in USA, France, England and Italy, and the Brazilian Navy relies on these manufacturers for depot-level maintenance. We develop a simulation model...

Interactive Inventory Monitoring

Science.gov (United States)

Garud, Sumedha

2013-01-01

Method and system for monitoring present location and/or present status of a target inventory item, where the inventory items are located on one or more inventory shelves or other inventory receptacles that communicate with an inventory base station through use of responders such as RFIDs. A user operates a hand held interrogation and display (lAD) module that communicates with, or is part of the base station to provide an initial inquiry. lnformation on location(s) of the larget invenlory item is also indicated visibly and/or audibly on the receptacle(s) for the user. Status information includes an assessment of operation readiness and a time, if known, that the specified inventory item or class was last removed or examined or modified. Presentation of a user access level may be required for access to the target inventgory item. Another embodiment provides inventory informatin for a stack as a sight-impaired or hearing-impaired person adjacent to that stack.

Measurements of instant-release source terms for 137Cs, 90Sr, 99Tc, 129I and 14C in used CANDU fuels

International Nuclear Information System (INIS)

Stroes-Gascoyne, S.

1996-01-01

Combined gap and grain-boundary inventories of 137 Cs, 129 I, 90 Sr, 99 Tc and 14 C were measured in 15 used CANDU fuel elements by leaching crushed fuel samples. A good correlation between the combined gap and grain-boundary inventories of 137 Cs and 129 I was found, suggesting that these fission products exhibit similar behavior in CANDU fuel. The expected correlation between combined gap and grain-boundary inventories of 137 Cs and 129 I with calculated fission-gas release to the gap and grain boundaries could only be confirmed for lower power fuels ( 90 Sr were higher than expected and showed no correlation with calculated fission-gas release. No values for the combined gap and grain-boundary inventories of 99 Tc were obtained because 99 Tc in used fuel samples is very insoluble and appears to require oxidation prior to dissolution. Combined gap and grain-boundary inventories of 14 C appeared to be independent of fuel power or burnup. (orig.)

Tritium recovery from fusion blankets using solid lithium compounds. I. Design and minimization of tritium inventory

International Nuclear Information System (INIS)

Powell, J.R.

1975-01-01

Tritium blanket inventories of 100 curies/MW(e) are readily achievable, and inventories as low as 10 curies/MW(e) are possible for blankets with small lithium compound particulates (less than or equal to 50μ) at T greater than or equal to 800 0 C. Of the three release modes [A - to the main coolant (e.g., He) stream; B - to a separate processing circuit; and C - to the plasma region], mode A appears optimum for blankets using gas-cooled metallic structures (e.g., Al, stainless), while mode C appears optimum for high temperature refractory (e.g., C, SiC) structures. The greater structural complexity of mode B makes it less attractive than modes A and C. No recovery method is required for mode C release. With mode A release, tritium inventory in the coolant circuits ranges from 1 to 10 curies/MW(e), depending on processing parameters. Tritium leak rates to the environment during normal operation can be kept to less than or equal to 10 -3 curies/MW(e) per day with low permeability barriers. In general, a mixture of T 2 and T 2 O is present in the coolant stream. Three methods of tritium recovery are examined: (1) Conversion to T 2 followed by absorption in a metal hydride bed. (2) Conversion to T 2 followed by condensation at approximately 6 0 K. (3) Conversion to T 2 O followed by condensation at approximately 100 0 K

Release Strategies: CMS approach for Development and Quality Assurance

CERN Document Server

Sexton-Kennedy, Elizabeth

2011-01-01

CMS has adopted a development model that tries to strike the correct balance between the needs of stability and a constant improvement; this talk will describe our experience with this model, and tell the story of how the commissioning of the CMS offline has proceeded through the perspective of the past year's releases.

Enhancements to inventory control procedures used at Koeberg nuclear power station

International Nuclear Information System (INIS)

Barker, M.P.; Adams, A.R.

1991-01-01

In industry today, industrial engineers are forced to seek new and innovative ideas to reduce costs. This can often be accomplished by simplified or modernized operational procedures. With the advancement in computer technology, operational procedures can be enhanced. Despite the fact that Eskom's Koeberg nuclear power station is one of a kind in Africa, it, like most other industries requires a large stock holding capacity. There are currently 25 000 stock items in the Koeberg Stores Information System. Controlling all of these items is no minor task and management is continually trying to optimise the inventory control procedures. One of these procedures is described. 3 refs., 1 fig

Fission product release from high gap-inventory LWR fuel under LOCA conditions

International Nuclear Information System (INIS)

Lorenz, R.A.; Collins, J.L.; Osborne, M.F.; Malinauskas, A.P.

1980-01-01

Fission product release tests were performed with light water reactor (LWR) fuel rod segments containing large amounts of cesium and iodine in the pellet-to-cladding gap space in order to check the validity of the previously published Source Term Model for this type of fuel. The model describes the release of fission product cesium and iodine from LWR fuel rods for controlled loss-of-coolant accident (LOCA) transients in the temperature range 500 to 1200 0 C. The basis for the model was test data obtained with simulated fuel rods and commercial fuel irradiated to high burnup but containing relatively small amounts of cesium and iodine in the pellet-to-cladding gap space

Global Inventory of Methane Hydrate: How Large is the Threat? (Invited)

Science.gov (United States)

Buffett, B. A.; Frederick, J. M.

2010-12-01

Methane hydrate is a dark horse in the science of climate change. The volume of methane sequestered in marine sediments is large enough to pose a potential threat, yet the expected contribution to future warming is not known. Part of the uncertainty lies in the poorly understood details of methane release from hydrate. Slow, diffusive loss of methane probably results in oxidation by sulfate and precipitation to CaCO3 in the sediments, with little effect on climate. Conversely, a direct release of methane into the atmosphere is liable to have strong and immediate consequences. Progress in narrowing the possibilities requires a better understanding of the mechanisms responsible for methane release. Improvements are also needed in our estimates of the hydrate inventory, as this sets a limit on the possible response. Several recent estimates of the hydrate inventory have been constructed using mechanistic models. Many of the model parameters (e.g. sedimentation rate and sea floor temperature) can be estimated globally, while others (e.g. vertical fluid flow) are not well known. Available observations can be used to estimate the poorly known parameters, but it is reasonable to question whether the results from a limited number of sites are representative of other locations. Fluid flow is a case in point because most hydrate locations are associated with upward flow. On the other hand, simple models of sediment compaction predict downward flow relative to the sea floor, which acts to impede hydrate formation. A variety of mechanisms can produce upward flow, including time-dependent sedimentation, seafloor topography, subsurface fractures, dehydration of clay minerals and gradual burial of methane hydrate below the stability zone. Each of these mechanisms makes specific predictions for the magnitude of flow and the proportion of sea floor that is likely to be affected. We assess the role of fluid flow on the present-day inventory and show that the current estimates for

Synergistic Extraction of Lactic Acid with Tri-n-Octylamine and Try-n-Butylphosphate

Energy Technology Data Exchange (ETDEWEB)

Matsumoto, Michiaki.; Yuba, Seiji.; Kondo, Kazuo. (Doshisha University, Department of Chemical Engineering and Materials Science (Japan))

1998-12-01

Synergistic extraction system of lactic acid is examined to develop to in situ extractive fermentation process. The addition of try-n-butyl phosphate(TBP) to the extraction system of lactic acid(HA) with tri-n-actylamine(TOA) diluted by hexane causes a large synergism. Extraction reaction with the mixed extractant is interpreted quite well based on the formation of mixed complex, HA[center dot]TOA[center dot]2TBP. Though the addition of hexane solution containing TBP and TOA to the culture of Lactobacillus rhamnosus results in low lactate production, some lactate is produced. (author)

Synergistic Extraction of Lactic Acid with Tri-n-Octylamine and Try-n-Butylphosphate

Energy Technology Data Exchange (ETDEWEB)

Matsumoto, Michiaki.; Yuba, Seiji.; Kondo, Kazuo. [Doshisha University, Department of Chemical Engineering and Materials Science (Japan)

1998-12-01

Synergistic extraction system of lactic acid is examined to develop to in situ extractive fermentation process. The addition of try-n-butyl phosphate(TBP) to the extraction system of lactic acid(HA) with tri-n-actylamine(TOA) diluted by hexane causes a large synergism. Extraction reaction with the mixed extractant is interpreted quite well based on the formation of mixed complex, HA{center_dot}TOA{center_dot}2TBP. Though the addition of hexane solution containing TBP and TOA to the culture of Lactobacillus rhamnosus results in low lactate production, some lactate is produced. (author)

Tri-Cities Index of Innovation and Technology

Energy Technology Data Exchange (ETDEWEB)

Fowler, Richard A.; Scott, Michael J.; Butner, Ryan S.

2011-01-17

In 2001 and 2004, the Economic Development Office of Pacific Northwest National Laboratory published companion reports to the Washington Technology Center Index studies that provided additional information on the Tri-Cities (Kennewick-Richland-Pasco) area of the state, its technology businesses, and important advantages that the Tri-Cities have as places to live and do business. These reports also compared the Tri-Cities area to other technology-based metropolitan areas in the Pacific Northwest and nation along critical dimensions known to be important to technology firms. This report updates the material in these earlier reports, and highlights a growing Tri-Cities metropolitan area.

Inventory and source term evaluation of Russian nuclear power plants for marine applications

International Nuclear Information System (INIS)

Reistad, O.; Oelgaard, P.L.

2006-04-01

This report discusses inventory and source term properties in regard to operation and possible releases due to accidents from Russian marine reactor systems. The first part of the report discusses relevant accidents on the basis of both Russian and western sources. The overview shows that certain vessels were much more accident prone compared to others, in addition, there have been a noteworthy reduction in accidents the last two decades. However, during the last years new types of incidents, such as collisions, has occurred more frequently. The second part of the study considers in detail the most important factors for the source term; reactor operational characteristics and the radionuclide inventory. While Russian icebreakers has been operated on a similar basis as commercial power plants, the submarines has different power cyclograms which results in considerable lower values for fission product inventory. Theoretical values for radionuclide inventory are compared with computed results using the modelling tool HELIOS. Regarding inventory of transuranic elements, the results of the calculations are discussed in detail for selected vessels. Criticality accidents, loss-of-cooling accidents and sinking accidents are considered, bases on actual experiences with these types of accident and on theoretical considerations, and source terms for these accidents are discussed in the last chapter. (au)

Inventory and source term evaluation of Russian nuclear power plants for marine applications

Energy Technology Data Exchange (ETDEWEB)

Reistad, O. [Norwegian Radiation Protection Authority (Norway); Oelgaard, P.L. [Risoe National Lab. (Denmark)

2006-04-15

This report discusses inventory and source term properties in regard to operation and possible releases due to accidents from Russian marine reactor systems. The first part of the report discusses relevant accidents on the basis of both Russian and western sources. The overview shows that certain vessels were much more accident prone compared to others, in addition, there have been a noteworthy reduction in accidents the last two decades. However, during the last years new types of incidents, such as collisions, has occurred more frequently. The second part of the study considers in detail the most important factors for the source term; reactor operational characteristics and the radionuclide inventory. While Russian icebreakers has been operated on a similar basis as commercial power plants, the submarines has different power cyclograms which results in considerable lower values for fission product inventory. Theoretical values for radionuclide inventory are compared with computed results using the modelling tool HELIOS. Regarding inventory of transuranic elements, the results of the calculations are discussed in detail for selected vessels. Criticality accidents, loss-of-cooling accidents and sinking accidents are considered, bases on actual experiences with these types of accident and on theoretical considerations, and source terms for these accidents are discussed in the last chapter. (au)

Pollutant Release and Transfer Register

International Nuclear Information System (INIS)

2008-01-01

Since 1974 a number of organisations have been working closely together in this pollutant register (PRTR) project to collect and formally establish the yearly releases of pollutants to air, water and soil in the Netherlands. Results of this project serve to underpin the national environmental policy. Data is in this way also provided for the many environmental reports to international organisations such as the European Union and the United Nations, e.g. the National Inventory Report for the Kyoto Protocol. This website shows the yearly releases (emissions) of the most important pollutants in the Netherlands. You can explore the emission data through various channels, such as maps, graphs and tables. But you can also download all the details into your own database. The data shown in this website is updated 2 to 3 times a year. The current release shows emissions for 1990, 1995, 2000, 2004, 2005 and 2006 The 2006 emissions are preliminary data and not yet shown in the maps. We expect to add an extra year in August 2008 [nl

Sensitivity of the global submarine hydrate inventory to scenarios of future climate change

Science.gov (United States)

Hunter, S. J.; Goldobin, D. S.; Haywood, A. M.; Ridgwell, A.; Rees, J. G.

2013-04-01

The global submarine inventory of methane hydrate is thought to be considerable. The stability of marine hydrates is sensitive to changes in temperature and pressure and once destabilised, hydrates release methane into sediments and ocean and potentially into the atmosphere, creating a positive feedback with climate change. Here we present results from a multi-model study investigating how the methane hydrate inventory dynamically responds to different scenarios of future climate and sea level change. The results indicate that a warming-induced reduction is dominant even when assuming rather extreme rates of sea level rise (up to 20 mm yr-1) under moderate warming scenarios (RCP 4.5). Over the next century modelled hydrate dissociation is focussed in the top ˜100m of Arctic and Subarctic sediments beneath business-as-usual scenario (RCP 8.5), upper estimates of resulting global sea-floor methane fluxes could exceed estimates of natural global fluxes by 2100 (>30-50TgCH4yr-1), although subsequent oxidation in the water column could reduce peak atmospheric release rates to 0.75-1.4 Tg CH4 yr-1.

TMAP-7 simulation of D2 thermal release data from Be co-deposited layers

International Nuclear Information System (INIS)

Baldwin, M.J.; Schwarz-Selinger, T.; Yu, J.H.; Doerner, R.P.

2013-01-01

The efficacy of (1) bake-out at 513 K and 623 K, and (2) thermal transient (10 ms) loading to up to 1000 K, is explored for reducing D inventory in 1 μm thick Be–D (D/Be ∼0.1) co-deposited layers formed at 323 K for experiment (1) and ∼500 K for experiment (2). D release data from co-deposits are obtained by thermal desorption and used to validate a model input into the Tritium Migration and Analysis Program 7 (TMAP). In (1), good agreement with experiment is found for a TMAP model encorporating traps of activation energies, 0.80 eV and 0.98 eV, whereas an additional 2 eV trap was required to model experiment (2). Thermal release is found to be trap limited, but simulations are optimal when surface recombination is taken into account. Results suggest that thick built-up co-deposited layers will hinder ITER inventory control, and that bake periods (∼1 day) will be more effective in inventory reduction than transient thermal loading

TMAP-7 simulation of D2 thermal release data from Be co-deposited layers

Science.gov (United States)

Baldwin, M. J.; Schwarz-Selinger, T.; Yu, J. H.; Doerner, R. P.

2013-07-01

The efficacy of (1) bake-out at 513 K and 623 K, and (2) thermal transient (10 ms) loading to up to 1000 K, is explored for reducing D inventory in 1 μm thick Be-D (D/Be ˜0.1) co-deposited layers formed at 323 K for experiment (1) and ˜500 K for experiment (2). D release data from co-deposits are obtained by thermal desorption and used to validate a model input into the Tritium Migration & Analysis Program 7 (TMAP). In (1), good agreement with experiment is found for a TMAP model encorporating traps of activation energies, 0.80 eV and 0.98 eV, whereas an additional 2 eV trap was required to model experiment (2). Thermal release is found to be trap limited, but simulations are optimal when surface recombination is taken into account. Results suggest that thick built-up co-deposited layers will hinder ITER inventory control, and that bake periods (˜1 day) will be more effective in inventory reduction than transient thermal loading.

Low and intermediate level waste in SFR-1. Reference Waste Inventory 2007

International Nuclear Information System (INIS)

Almkvist, Lisa; Gordon, Ann

2007-11-01

The objective with this report is to describe all the waste and the waste package that is expected to be deposited in SFR 1 at the time of closure. The report will form the basis for the release calculation in the safety analysis for SFR 1. Three different scenarios are explored in this report; the waste inventory is based on an estimated operational lifetime of the Swedish nuclear power plants of 50 and 60 years and that closure of the SFR 1 repository will take place in 2040 or 2050 respectively. The third scenario is where the repository is full (one part where the activity adds up to 1016 Bq and one part where the repository is considered full regarding volume). In the report, data about geometries, weights, materials, chemicals and radionuclide are given. No chemotoxic material has been identified in the waste. The inventory is estimated using the Prosit-interface which extracts information from the Triumf database. The inventory is based on so called 'waste types' and the waste types' 'reference waste package'. The reference waste package combined with a prognosis of the number of waste packages to be delivered to SFR 1 gives the final waste inventory for SFR 1. All reference waste packages are thoroughly described in the appendices of this report. The reference waste packages are as far as possible based on actual experiences and measurements. The radionuclide inventory is also based on actual measurements. The inventory is based on measurements of 60 Co and 137 Cs in waste packages and on measurements of 239 Pu and 240 Pu in reactor water. Other nuclides in the inventory are calculated with correlation factors

Exposure to tri-o-cresyl phosphate detected in jet airplane passengers

International Nuclear Information System (INIS)

Liyasova, Mariya; Li, Bin; Schopfer, Lawrence M.; Nachon, Florian; Masson, Patrick; Furlong, Clement E.; Lockridge, Oksana

2011-01-01

The aircraft cabin and flight deck ventilation are supplied from partially compressed unfiltered bleed air directly from the engine. Worn or defective engine seals can result in the release of engine oil into the cabin air supply. Aircrew and passengers have complained of illness following such “fume events”. Adverse health effects are hypothesized to result from exposure to tricresyl phosphate mixed esters, a chemical added to jet engine oil and hydraulic fluid for its anti-wear properties. Our goal was to develop a laboratory test for exposure to tricresyl phosphate. The assay was based on the fact that the active-site serine of butyrylcholinesterase reacts with the active metabolite of tri-o-cresyl phosphate, cresyl saligenin phosphate, to make a stable phosphorylated adduct with an added mass of 80 Da. No other organophosphorus agent makes this adduct in vivo on butyrylcholinesterase. Blood samples from jet airplane passengers were obtained 24–48 h after completing a flight. Butyrylcholinesterase was partially purified from 25 ml serum or plasma, digested with pepsin, enriched for phosphorylated peptides by binding to titanium oxide, and analyzed by mass spectrometry. Of 12 jet airplane passengers tested, 6 were positive for exposure to tri-o-cresyl phosphate that is, they had detectable amounts of the phosphorylated peptide FGEpSAGAAS. The level of exposure was very low. No more than 0.05 to 3% of plasma butyrylcholinesterase was modified. None of the subjects had toxic symptoms. Four of the positive subjects were retested 3 to 7 months following their last airplane trip and were found to be negative for phosphorylated butyrylcholinesterase. In conclusion, this is the first report of an assay that detects exposure to tri-o-cresyl phosphate in jet airplane travelers. -- Highlights: ► Travel on jet airplanes is associated with an illness, aerotoxic syndrome. ► A possible cause is exposure to tricresyl phosphate in engine lubricating oil. ► A blood

Exposure to tri-o-cresyl phosphate detected in jet airplane passengers

Energy Technology Data Exchange (ETDEWEB)

Liyasova, Mariya, E-mail: mliyasov@unmc.edu [Eppley Institute, University of Nebraska Medical Center, Omaha, NE 68198-5950 (United States); Department of Environmental, Agricultural, and Occupational Health, University of Nebraska Medical Center, Omaha, NE (United States); Li, Bin, E-mail: binli@unmc.edu [Eppley Institute, University of Nebraska Medical Center, Omaha, NE 68198-5950 (United States); Schopfer, Lawrence M., E-mail: lmschopf@unmc.edu [Eppley Institute, University of Nebraska Medical Center, Omaha, NE 68198-5950 (United States); Nachon, Florian, E-mail: fnachon@nachon.net [Departement de Toxicologie, Institut de Recherche Biomedicale des Armees, 24 avenue des Marquis du Gresivaudan, 38702 La Tronche (France); Masson, Patrick, E-mail: pmasson@unmc.edu [Departement de Toxicologie, Institut de Recherche Biomedicale des Armees, 24 avenue des Marquis du Gresivaudan, 38702 La Tronche (France); Eppley Institute, University of Nebraska Medical Center, Omaha, NE 68198-5950 (United States); Furlong, Clement E., E-mail: clem@uw.edu [Department of Medicine (Div. Medical Genetics) and Genome Sciences, University of Washington, Seattle, WA 98195 (United States); Lockridge, Oksana, E-mail: olockrid@unmc.edu [Eppley Institute, University of Nebraska Medical Center, Omaha, NE 68198-5950 (United States); Department of Environmental, Agricultural, and Occupational Health, University of Nebraska Medical Center, Omaha, NE (United States)

2011-11-15

The aircraft cabin and flight deck ventilation are supplied from partially compressed unfiltered bleed air directly from the engine. Worn or defective engine seals can result in the release of engine oil into the cabin air supply. Aircrew and passengers have complained of illness following such 'fume events'. Adverse health effects are hypothesized to result from exposure to tricresyl phosphate mixed esters, a chemical added to jet engine oil and hydraulic fluid for its anti-wear properties. Our goal was to develop a laboratory test for exposure to tricresyl phosphate. The assay was based on the fact that the active-site serine of butyrylcholinesterase reacts with the active metabolite of tri-o-cresyl phosphate, cresyl saligenin phosphate, to make a stable phosphorylated adduct with an added mass of 80 Da. No other organophosphorus agent makes this adduct in vivo on butyrylcholinesterase. Blood samples from jet airplane passengers were obtained 24-48 h after completing a flight. Butyrylcholinesterase was partially purified from 25 ml serum or plasma, digested with pepsin, enriched for phosphorylated peptides by binding to titanium oxide, and analyzed by mass spectrometry. Of 12 jet airplane passengers tested, 6 were positive for exposure to tri-o-cresyl phosphate that is, they had detectable amounts of the phosphorylated peptide FGEpSAGAAS. The level of exposure was very low. No more than 0.05 to 3% of plasma butyrylcholinesterase was modified. None of the subjects had toxic symptoms. Four of the positive subjects were retested 3 to 7 months following their last airplane trip and were found to be negative for phosphorylated butyrylcholinesterase. In conclusion, this is the first report of an assay that detects exposure to tri-o-cresyl phosphate in jet airplane travelers. -- Highlights: Black-Right-Pointing-Pointer Travel on jet airplanes is associated with an illness, aerotoxic syndrome. Black-Right-Pointing-Pointer A possible cause is exposure to

A systems approach to inventory management of repairables in the Navy

OpenAIRE

Apple, Chris Leon

1985-01-01

Approved for public release; distribution is unlimited This thesis develops an inventory model for repairable items which integrates the shipboard protection level into the wholesale stock level computations. It uses mean supply response time (MSRT) as its measure of effectiveness and provides methods for computing either the required wholesale stock level given a MSRT goal or for minimizing the system MSRT subject to budgetary constraints. Examples are provided which demons...

Generation and release of radioactive gases in LLW disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Yim, M.S. [Harvard School Public Health, Boston, MA (United States); Simonson, S.A. [Massachusetts Institute of Technology, Cambridge, MA (United States)

1995-02-01

The atmospheric release of radioactive gases from a generic engineered LLW disposal facility and its radiological impacts were examined. To quantify the generation of radioactive gases, detailed characterization of source inventory for carbon-14, tritium, iodine-129, krypton-85, and radon-222, was performed in terms of their activity concentrations; their distribution within different waste classes, waste forms and containers; and their subsequent availability for release in volatile or gaseous form. The generation of gases was investigated for the processes of microbial activity, radiolysis, and corrosion of waste containers and metallic components in wastes. The release of radionuclides within these gases to the atmosphere was analyzed under the influence of atmospheric pressure changes.

Nuclear, thermo-mechanical and tritium release analysis of ITER breeding blanket

International Nuclear Information System (INIS)

Kosaku, Yasuo; Kuroda, Toshimasa; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Miki, Nobuharu; Akiba, Masato

2003-06-01

The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket. With respect to the neutronics analysis, the detailed analyses of the distribution of the nuclear heating rate and TBR have been performed in 2D model using MCNP to clarify the input data for the tritium inventory and release rate analyses and thermo-mechanical analyses. With respect to the tritium inventory and release behavior analysis, the parametric analyses for selection of purge gas flow rate were carried out from the view point of pressure drop and the tritium inventory/release performance for Li 2 TiO 3 breeder. The analysis result concluded that purge gas flow rate can be set to conventional flow rate setting (88 l/min per module) to 1/10 of that to save the purge gas flow and minimize the size of purge gas pipe. However, it is necessary to note that more tritium is transformed to HTO (chemical form of water) in case of Li 2 TiO 3 compared to other breeder materials. With respect to the thermo-mechanical analyses of the pebble bed blanket structure, the analyses have been performed by ABAQUS with 2D model derived from one of eight facets of a blanket module, based on the reference design. Analyses were performed to identify the temperature distribution incorporating the pebble bed mechanical simulation and influence of mechanical behavior to the thermal behavior. The result showed that the maximum temperature in the breeding material was 617degC in the first row of breeding rods and the minimum temperature was 328

TMAP-7 simulation of D{sub 2} thermal release data from Be co-deposited layers

Energy Technology Data Exchange (ETDEWEB)

Baldwin, M.J., E-mail: mbaldwin@ferp.ucsd.edu [Center for Energy Research, University of California at San Diego, La Jolla, CA 92093-0417 (United States); Schwarz-Selinger, T. [Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, 85748 Garching (Germany); Yu, J.H. [Center for Energy Research, University of California at San Diego, La Jolla, CA 92093-0417 (United States); Doerner, R.P., E-mail: rdoerner@ucsd.edu [Center for Energy Research, University of California at San Diego, La Jolla, CA 92093-0417 (United States)

2013-07-15

The efficacy of (1) bake-out at 513 K and 623 K, and (2) thermal transient (10 ms) loading to up to 1000 K, is explored for reducing D inventory in 1 μm thick Be–D (D/Be ∼0.1) co-deposited layers formed at 323 K for experiment (1) and ∼500 K for experiment (2). D release data from co-deposits are obtained by thermal desorption and used to validate a model input into the Tritium Migration and Analysis Program 7 (TMAP). In (1), good agreement with experiment is found for a TMAP model encorporating traps of activation energies, 0.80 eV and 0.98 eV, whereas an additional 2 eV trap was required to model experiment (2). Thermal release is found to be trap limited, but simulations are optimal when surface recombination is taken into account. Results suggest that thick built-up co-deposited layers will hinder ITER inventory control, and that bake periods (∼1 day) will be more effective in inventory reduction than transient thermal loading.

Safety analysis and inventory control of transuranic and low-level waste in common storage

International Nuclear Information System (INIS)

Porten, D.R.; Bonner, A.L.; Joyce, J.P.

1993-01-01

This paper describes a methodology developed For the inventory control of low-level waste (LLW) and transuranic (TRU) waste, when both are stored in the same location, and both contribute to an inventory constrained by safety considerations. Development of the method arose from the necessity to make safety analysis calculations for the addition of LLW, in quantities greater than existing inventory limits would allow when stored with TRU waste, in the Hanford Central Waste Complex (CWC)-Ensuring that the dose consequences of credible releases are maintained at low-hazard limits or less, was used to allow greater than Type A quantities of LLW into the CWC. Basically, what happens is the original limited amount of TRU allowed is reduced by some equivalent amount of LLW introduced. The total quantity of TRU, and LLW in excess of Type A quantities, must be administratively maintained via curie equivalency Factors to ensure operation as a low-hazard Facility. The ''equivalency'' between TRU and LLW proposed here is specific only to the CWC, but the methodology can be used for other specific applications, such as TRU and LLW storage or handling facilities where inventory limits must be enforced or where a simplified inventory system is required

Low and intermediate level waste in SFR-1. Reference Waste Inventory 2007

Energy Technology Data Exchange (ETDEWEB)

Almkvist, Lisa (Vattenfall Power Consultant AB, Stockholm (SE)); Gordon, Anna (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE))

2007-11-15

The objective with this report is to describe all the waste and the waste package that is expected to be deposited in SFR 1 at the time of closure. The report will form the basis for the release calculation in the safety analysis for SFR 1. Three different scenarios are explored in this report; the waste inventory is based on an estimated operational lifetime of the Swedish nuclear power plants of 50 and 60 years and that closure of the SFR 1 repository will take place in 2040 or 2050 respectively. The third scenario is where the repository is full (one part where the activity adds up to 1016 Bq and one part where the repository is considered full regarding volume). In the report, data about geometries, weights, materials, chemicals and radionuclide are given. No chemotoxic material has been identified in the waste. The inventory is estimated using the Prosit-interface which extracts information from the Triumf database. The inventory is based on so called 'waste types' and the waste types' 'reference waste package'. The reference waste package combined with a prognosis of the number of waste packages to be delivered to SFR 1 gives the final waste inventory for SFR 1. All reference waste packages are thoroughly described in the appendices of this report. The reference waste packages are as far as possible based on actual experiences and measurements. The radionuclide inventory is also based on actual measurements. The inventory is based on measurements of 60Co and 137Cs in waste packages and on measurements of 239Pu and 240Pu in reactor water. Other nuclides in the inventory are calculated with correlation factors

The IAEA inventory databases related to radioactive material entering the marine environment

International Nuclear Information System (INIS)

Rastogi, R.C.; Sjoeblom, K.L.

1999-01-01

Contracting Parties to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter (LC 1972) have requested the IAEA to develop an inventory of radioactive material entering the marine environment from all sources. The rationale for developing and maintaining the inventory is related to its use as an information base with which the impact of radionuclides entering the marine environment from different sources can be assessed and compared. Five anthropogenic sources of radionuclides entering the marine environment can be identified. These sources are: radioactive waste disposal at sea; accidents and losses at sea involving radioactive material; discharge of low level liquid effluents from land-based nuclear facilities; the fallout from nuclear weapons testing; and accidental releases from land-based nuclear facilities. The first two of these sources are most closely related to the objective of the LC 1972 and its request to the IAEA. This paper deals with the Agency's work on developing a database on radioactive material entering the marine environment from these two sources. The database has the acronym RAMEM (RAdioactive Material Entering the Marine Environment). It includes two modules: inventory of radioactive waste disposal at sea and inventory of accidents and losses at sea involving radioactive material

Procedure for taking physical inventories

International Nuclear Information System (INIS)

Anon.

1981-01-01

This session is intended to apprise one of the various aspects of procedures and routines that Exxon Nuclear uses with respect to its nuclear materials physical inventory program. The presentation describes how plant physical inventories are planned and taken. The description includes the planning and preparation for taking the inventory, the clean-out procedures for converting in-process material to measurable items, the administrative procedures for establishing independent inventory teams and for inventorying each inventory area, the verification procedures used to include previously measured tamper-safed items in the inventory, and lastly, procedures used to reconcile the inventory and calculate MUF (materials unaccounted for). The purpose of the session is to enable participants to: (1) understand the planning and pre-inventorty procedures and their importance; (2) understand the need for and the required intensity of clean-out procedures; (3) understand how inventory teams are formed, and how the inventory is conducted; (4) understand the distinction between inventory previously measured tamper-safed items and other materials not so characterized; (5) understand the reconciliation procedures; and (6) calculate a MUF given the book and inventory results

Formaldehyde-releasers: relationship to formaldehyde contact allergy. Contact allergy to formaldehyde and inventory of formaldehyde-releasers

DEFF Research Database (Denmark)

de Groot, Anton C; Flyvholm, Mari-Ann; Lensen, Gerda

2009-01-01

in the literature as formaldehyde-releasers, data are inadequate to consider them as such beyond doubt. Several (nomenclature) mistakes and outdated information are discussed. Formaldehyde and formaldehyde allergy are reviewed: applications, exposure scenarios, legislation, patch testing problems, frequency....... The frequency of contact allergy to formaldehyde is consistently higher in the USA (8-9%) than in Europe (2-3%). Patch testing with formaldehyde is problematic; the currently used 1% solution may result in both false-positive and false-negative (up to 40%) reactions. Determining the relevance of patch test...

Synthesis, Structural, Viscosimetric, And Rheological Study, of A New Trifunctional Phosphorus Epoxyde Prepolymer , Tri-Glycidyl Ether Tri-Mercaptoethanol Of Phosphore (TGETMEP

Directory of Open Access Journals (Sweden)

Atiqa Bekhta

2016-10-01

Full Text Available The aim of our work is to synthesize a new phosphorus tri-functional epoxy resin tri-glycidyl ether tri-mercaptoethanol of phosphorus (TGETMEP in two stages. In the first stage, we got the precursor molecule of the epoxy matrix tri-mercaptoethanol phosphate (METR. The second step led us to the synthesis of tri-functional resin TMEP condensation with epichlorohydrin. The standard TGETMEP resin was characterized by the Fourier infrared transformation (FTIR and nuclear magnetic resonance (NMR, on one hand. The viscosimetric analysis was investigated by the Hebbelod capillary viscometer and rheometer Rheomat 01, on the other hand. The cross-linked resins and tertiary formulated composites have been studied by the rheometer 01 which was observed by means of SEM.

Development and Content Validation of the Transition Readiness Inventory Item Pool for Adolescent and Young Adult Survivors of Childhood Cancer.

Science.gov (United States)

Schwartz, Lisa A; Hamilton, Jessica L; Brumley, Lauren D; Barakat, Lamia P; Deatrick, Janet A; Szalda, Dava E; Bevans, Katherine B; Tucker, Carole A; Daniel, Lauren C; Butler, Eliana; Kazak, Anne E; Hobbie, Wendy L; Ginsberg, Jill P; Psihogios, Alexandra M; Ver Hoeve, Elizabeth; Tuchman, Lisa K

2017-10-01

The development of the Transition Readiness Inventory (TRI) item pool for adolescent and young adult childhood cancer survivors is described, aiming to both advance transition research and provide an example of the application of NIH Patient Reported Outcomes Information System methods. Using rigorous measurement development methods including mixed methods, patient and parent versions of the TRI item pool were created based on the Social-ecological Model of Adolescent and young adult Readiness for Transition (SMART). Each stage informed development and refinement of the item pool. Content validity ratings and cognitive interviews resulted in 81 content valid items for the patient version and 85 items for the parent version. TRI represents the first multi-informant, rigorously developed transition readiness item pool that comprehensively measures the social-ecological components of transition readiness. Discussion includes clinical implications, the application of TRI and the methods to develop the item pool to other populations, and next steps for further validation and refinement. © The Author 2017. Published by Oxford University Press on behalf of the Society of Pediatric Psychology. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com

Inventory - Dollars and sense

International Nuclear Information System (INIS)

Samson, J.R.

1992-01-01

Nuclear utilities are becoming more aware of the importance of having an inventory investment that supports two opposing philosophies. The business philosophy wants a minimal inventory investment to support a better return on invested dollars. This increase in return comes from having the dollars available to invest versus having the money tied up in inventory sitting on the shelf. The opposing viewpoint is taken by maintenance/operations organizations, which desire the maximum inventory available on-site to repair any component at any time to keep the units on-line at all times. Financial managers also want to maintain cash flow throughout operations so that plants run without interruptions. Inventory management is therefore a mixture of financial logistics with an operation perspective in mind. A small amount of common sense and accurate perception also help. The challenge to the materials/inventory manager is to optimize effectiveness of the inventory by having high material availability at the lowest possible cost

Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions

Energy Technology Data Exchange (ETDEWEB)

González-Robles, E., E-mail: ernesto.gonzalez-robles@kit.edu [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Metz, V. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Wegen, D.H. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Herm, M. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Papaioannou, D. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Bohnert, E. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Gretter, R. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Müller, N. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Nasyrow, R.; Weerd, W. de; Wiss, T. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Kienzler, B. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany)

2016-10-15

During reactor operation the fission gases Kr and Xe are formed within the UO{sub 2} matrix of nuclear fuel. Their quantification is important to evaluate their impact on critical parameters regarding the fuel behaviour during irradiation and (long-term) interim storage, such as internal pressure of the fuel rod and fuel swelling. Moreover the content of Kr and Xe in the plenum of a fuel rod and their content in the UO{sub 2} fuel itself are widely used as indicators for the release properties of {sup 129}I, {sup 137}Cs, and other safety relevant radionuclides with respect to final disposal of spent nuclear fuel. The present study deals with the fission gas release from spent nuclear fuel exposed to simulated groundwater in comparison with the fission gas previously released to the fuel rod plenum during irradiation in reactor. In a unique approach we determined both the Kr and Xe inventories in the plenum by means of a puncturing test and in leaching experiments with a cladded fuel pellet and fuel fragments in bicarbonate water under 3.2 bar H{sub 2} overpressure. The fractional inventory of the fission gases released during irradiation into the plenum was (8.3 ± 0.9) %. The fraction of inventory of fission gases released during the leaching experiments was (17 ± 2) % after 333 days of leaching of the cladded pellet and (25 ± 2) % after 447 days of leaching of the fuel fragments, respectively. The relatively high release of fission gases in the experiment with fuel fragments was caused by the increased accessibility of water to the Kr and Xe occluded in the fuel.

Exposure to tri-o-cresyl phosphate detected in jet airplane passengers.

Science.gov (United States)

Liyasova, Mariya; Li, Bin; Schopfer, Lawrence M; Nachon, Florian; Masson, Patrick; Furlong, Clement E; Lockridge, Oksana

2011-11-01

The aircraft cabin and flight deck ventilation are supplied from partially compressed unfiltered bleed air directly from the engine. Worn or defective engine seals can result in the release of engine oil into the cabin air supply. Aircrew and passengers have complained of illness following such "fume events". Adverse health effects are hypothesized to result from exposure to tricresyl phosphate mixed esters, a chemical added to jet engine oil and hydraulic fluid for its anti-wear properties. Our goal was to develop a laboratory test for exposure to tricresyl phosphate. The assay was based on the fact that the active-site serine of butyrylcholinesterase reacts with the active metabolite of tri-o-cresyl phosphate, cresyl saligenin phosphate, to make a stable phosphorylated adduct with an added mass of 80 Da. No other organophosphorus agent makes this adduct in vivo on butyrylcholinesterase. Blood samples from jet airplane passengers were obtained 24-48 h after completing a flight. Butyrylcholinesterase was partially purified from 25 ml serum or plasma, digested with pepsin, enriched for phosphorylated peptides by binding to titanium oxide, and analyzed by mass spectrometry. Of 12 jet airplane passengers tested, 6 were positive for exposure to tri-o-cresyl phosphate that is, they had detectable amounts of the phosphorylated peptide FGEpSAGAAS. The level of exposure was very low. No more than 0.05 to 3% of plasma butyrylcholinesterase was modified. None of the subjects had toxic symptoms. Four of the positive subjects were retested 3 to 7 months following their last airplane trip and were found to be negative for phosphorylated butyrylcholinesterase. In conclusion, this is the first report of an assay that detects exposure to tri-o-cresyl phosphate in jet airplane travelers. Copyright © 2011 Elsevier Inc. All rights reserved.

Inventory control strategies

International Nuclear Information System (INIS)

Primrose, D.

1998-01-01

Finning International Inc. is in the business of selling, financing and servicing Caterpillar and complementary equipment. Its main markets are in western Canada, Britain and Chile. This paper discusses the parts inventory strategies system for Finning (Canada). The company's territory covers British Columbia, Alberta, the Yukon and the Northwest Territories. Finning's parts inventory consists of 80,000 component units valued at more than $150 M. Distribution centres are located in Langley, British Columbia and Edmonton, Alberta. To make inventory and orders easier to control, Finning has designed a computer-based system, with software written exclusively for Caterpillar dealers. The system makes use of a real time electronic interface with all Finning locations, plus all Caterpillar facilities and other dealers in North America. Details of the system are discussed, including territorial stocking procedures, addition to stock, exhaustion of stock, automatic/suggest order controls, surplus inventory management, and procedures for jointly managed inventory. 3 tabs., 1 fig

WW LCI v2: A second-generation life cycle inventory model for chemicals discharged to wastewater systems.

Science.gov (United States)

Kalbar, Pradip P; Muñoz, Ivan; Birkved, Morten

2018-05-01

We present a second-generation wastewater treatment inventory model, WW LCI 2.0, which on many fronts represents considerable advances compared to its previous version WW LCI 1.0. WW LCI 2.0 is a novel and complete wastewater inventory model integrating WW LCI 1.0, i.e. a complete life cycle inventory, including infrastructure requirement, energy consumption and auxiliary materials applied for the treatment of wastewater and disposal of sludge and SewageLCI, i.e. fate modelling of chemicals released to the sewer. The model is expanded to account for different wastewater treatment levels, i.e. primary, secondary and tertiary treatment, independent treatment by septic tanks and also direct discharge to natural waters. Sludge disposal by means of composting is added as a new option. The model also includes a database containing statistics on wastewater treatment levels and sludge disposal patterns in 56 countries. The application of the new model is demonstrated using five chemicals assumed discharged to wastewater systems in four different countries. WW LCI 2.0 model results shows that chemicals such as diethylenetriamine penta (methylene phosphonic acid) (DTPMP) and Diclofenac, exhibit lower climate change (CC) and freshwater ecotoxicity (FET) burdens upon wastewater treatment compared to direct discharge in all country scenarios. Results for Ibuprofen and Acetaminophen (more readily degradable) show that the CC burden depends on the country-specific levels of wastewater treatment. Higher treatment levels lead to lower CC and FET burden compared to direct discharge. WW LCI 2.0 makes it possible to generate complete detailed life cycle inventories and fate analyses for chemicals released to wastewater systems. Our test of the WW LCI 2.0 model with five chemicals illustrates how the model can provide substantially different outcomes, compared to conventional wastewater inventory models, making the inventory dependent upon the atomic composition of the molecules

Development and Testing of the Solar System Concept Inventory

Science.gov (United States)

Hornstein, Seth D.; Prather, E. E.; English, T. R.; Desch, S. M.; Keller, J. M.; Collaboration of Astronomy Teaching Scholars CATS

2011-01-01

Trying to assess if our students really understand the ideas we present in class can be difficult. Concept inventories are research-validated assessment tools that can provide us with data to better understand whether we are successful in the classroom. The idea for the Solar System Concept Inventory (SSCI) was born after realizing that no concept inventory currently available covered details regarding the formation and evolution of our solar system. Topics were selected by having faculty identify the key concepts they address when teaching about the solar system and interviewing students in order to identify common naive ideas and reasoning difficulties relating to these key topics. Beginning in fall of 2008, a national multi-institutional field test began which would eventually involve nearly 2500 students and 17 instructors from 10 different institutions. After each round of testing, a group of instructors from multiple institutions around the country worked together to analyze the data and revise or eliminate underperforming questions. Each question was examined using a combination of point biserial, percent correct on the pre-test, and item difficulty to determine if the question was properly differentiating student understanding while also ensuring the question was not too easy or too hard. In this talk, I will present an overall outline of the development of the SSCI as well as the final testing results. The final version of the SSCI can be found at http://casa.colorado.edu/ hornstei/ssci/. This material is based upon work supported by the National Science Foundation under Grant No. 0715517, a CCLI Phase III Grant for the Collaboration of Astronomy Teaching Scholars (CATS). Any findings expressed in this material are those of the authors and do not necessarily reflect the views of the NSF.

INVENTORY MANAGEMENT IN THE ENTERPRISE THROUGH THE APPLICATION OF IFRS 2 INVENTORIES

Directory of Open Access Journals (Sweden)

Svetlozar Stefanov

2016-07-01

Full Text Available The focus in the article is on the issues of valuation and presentation of the inventories under the meaning on the International Accounting Standard 2 Inventories. The Standard provides guidance on the determination of costs of finished products and its recognition as and expense in the production and sale finished products, including guidance for determination of the net realizable value. The latter is defined as the estimated selling price less the estimated costs of completion and estimated costs necessary to make the sale. The cost of inventories comprises all costs of purchase, cost of conversion and other costs incurred in bringing the inventories to a condition suitable for subsequent use. The amount of the cost for materials used or products sold and the finished product is determined using one of the following methods: a specifically defined value, first-in � first out or weighted average cost of lots delivered. When inventories are sold, the carrying amount of those inventories is recognized as an expense in the period in which the related sales revenue is recognized. The amount of any write-down of inventories to net realizable value is recorded as a current expense and is recognized as an expense in the period the write-down occurs.

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Energy Technology Data Exchange (ETDEWEB)

González-Robles, E., E-mail: ernesto.gonzalez-robles@kit.edu [CTM Centre Tecnològic, Plaça de la Ciència 2, 08243 Manresa (Spain); Serrano-Purroy, D. [European Commission - EC, Joint Research Centre (JRC), Institute for Transuranium Elements - ITU, Postfach 2340, D-76125 Karlsruhe (Germany); Sureda, R. [CTM Centre Tecnològic, Plaça de la Ciència 2, 08243 Manresa (Spain); Casas, I. [Chemical Engineering Department, Universitat Politècnica de Catalunya, Av. Diagonal 647, 08028 Barcelona (Spain); Pablo, J. de [CTM Centre Tecnològic, Plaça de la Ciència 2, 08243 Manresa (Spain); Chemical Engineering Department, Universitat Politècnica de Catalunya, Av. Diagonal 647, 08028 Barcelona (Spain)

2015-10-15

The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, and the grain boundaries and, if present, in the high burn-up structure (HBS). The values calculated from this theoretical approach correspond to an upper limit that likely does not correspond to what it will be expected to be instantaneously released in the real system. Trying to ascertain this IRF from an experimental point of view, static leaching experiments have been carried out with two commercial UO{sub 2} spent nuclear fuels (SNF): one from a pressurized water reactor (PWR), labelled PWR, with an average burn-up (BU) of 52 MWd/kgU and fission gas release (FGR) of 23.1%, and one from a boiling water reactor (BWR), labelled BWR, with an average BU of and 53 MWd/kgU and FGR of 3.9%. One sample of each SNF, consisting of fuel and cladding, has been leached in bicarbonate water during one year under oxidizing conditions at room temperature (25 ± 5)°C. The behaviour of the concentration measured in solution can be divided in two according to the release rate. All radionuclides presented an initial release rate that after some days levels down to a slower second one, which remains constant until the end of the experiment. Cumulative fraction of inventory in aqueous phase (FIAP{sub c}) values has been calculated. Results show faster release in the case of the PWR SNF. In both cases Np, Pu, Am, Cm, Y, Tc, La and Nd dissolve congruently with U, while dissolution of Zr, Ru and Rh is slower. Rb, Sr, Cs and Mo, dissolve faster than U. The IRF of Cs at 10 and 200 days has been calculated, being (3.10 ± 0.62) and (3.66 ± 0.73) for PWR fuel, and (0.35 ± 0.07) and (0.51 ± 0.10) for BWR fuel.

Toward an Assessment of the Global Inventory of Present-Day Mercury Releases to Freshwater Environments

Directory of Open Access Journals (Sweden)

David Kocman

2017-02-01

Full Text Available Aquatic ecosystems are an essential component of the biogeochemical cycle of mercury (Hg, as inorganic Hg can be converted to toxic methylmercury (MeHg in these environments and reemissions of elemental Hg rival anthropogenic Hg releases on a global scale. Quantification of effluent Hg releases to aquatic systems globally has focused on discharges to the global oceans, rather than contributions to freshwater systems that affect local exposures and risks associated with MeHg. Here we produce a first-estimate of sector-specific, spatially resolved global aquatic Hg discharges to freshwater systems. We compare our release estimates to atmospheric sources that have been quantified elsewhere. By analyzing available quantitative and qualitative information, we estimate that present-day global Hg releases to freshwater environments (rivers and lakes associated with anthropogenic activities have a lower bound of ~1000 Mg· a−1. Artisanal and small-scale gold mining (ASGM represents the single largest source, followed by disposal of mercury-containing products and domestic waste water, metal production, and releases from industrial installations such as chlor-alkali plants and oil refineries. In addition to these direct anthropogenic inputs, diffuse inputs from land management activities and remobilization of Hg previously accumulated in terrestrial ecosystems are likely comparable in magnitude. Aquatic discharges of Hg are greatly understudied and further constraining associated data gaps is crucial for reducing the uncertainties in the global biogeochemical Hg budget.

World Glacier Inventory

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The World Glacier Inventory (WGI) contains information for over 130,000 glaciers. Inventory parameters include geographic location, area, length, orientation,...

Investigation of Effectiveness of Order Review and Release Models in Make to Order Supply Chain

Directory of Open Access Journals (Sweden)

Kundu Kaustav

2016-01-01

Full Text Available Nowadays customisation becomes more common due to vast requirement from the customers for which industries are trying to use make-to-order (MTO strategy. Due to high variation in the process, workload control models are extensively used for jobshop companies which usually adapt MTO strategy. Some authors tried to implement workload control models, order review and release systems, in non-repetitive manufacturing companies, where there is a dominant flow in production. Those models are better in shop floor but their performances are never been investigated in high variation situations like MTO supply chain. This paper starts with the introduction of particular issues in MTO companies and a general overview of order review and release systems widely used in the industries. Two order review and release systems, the Limited and Balanced models, particularly suitable for flow shop system are applied to MTO supply chain, where the processing times are difficult to estimate due to high variation. Simulation results show that the Balanced model performs much better than the Limited model if the processing times can be estimated preciously.

The Game of Tri

Science.gov (United States)

Haggard, Gary; Schonberger, Ann Koch

1977-01-01

The paper-and-pencil game "Tri" is described. The authors argue that students gain logical skills by playing the game, and that the game lends itself to the introduction of diverse mathematical ideas. (SD)

General technical requirements (GTR) for inventory monitoring systems (IMS) for the trilateral initiative

International Nuclear Information System (INIS)

Pshakin, Gennady M.; Kuleshov, I.; Shea, T.; Puckett, J.M.; Zhukov, I.; Mangan, Dennis L.; Matter, John C.; Waddoups, I.; Smathers, D.; Abhold, M.E.; Hsue, S.-T.; Chiaro, P.

2002-01-01

Pursuant to the Trilateral Initiative, the three parties (The Russian Federation, the United States, and the International Atomic Energy Agency) have been engaged in discussions concerning the structure of reliable monitoring systems for storage facilities having large inventories. The intent of these monitoring systems is to provide the capability for the IAEA to maintain continuity of knowledge in a sufficiently reliable manner that should there be equipment failure, loss of continuity of knowledge would be restricted to a small population of the inventory, and thus reinventory of the stored items would be minimized These facility-specific monitoring systems, referred to as Inventory Monitoring Systems (IMS) are to provide the principal means for the M A to assure that the containers of fissile material remain accounted under the Verification Agreements which are to be concluded between the IAEA and the Russian Federation and the lAEA and the United States for the verification of weapon-origin and other fissile material specified by each State as released from its defense programs. A technical experts working group for inventory monitoring systems has been meeting since Feb- of 2000 to formulate General Technical Requirements (GTR) for Inventory Monitoring Systems for the Trilateral Initiative. Although provisional agreement has been reached by the three parties concerning the GTR, it is considered a living document that can be updated as warranted by the three parties. This paper provides a summary of the GTR as it currently exists.

Vendor-managed inventory

DEFF Research Database (Denmark)

Govindan, Kannan

2013-01-01

Vendor-managed inventory (VMI) represents the methodology through which the upstream stage of a supply chain (vendor) takes responsibility for managing the inventories at the downstream stage (customer) based on previously agreed limits. VMI is another method by which supply chains can be managed...... review, we have identified six dimensions of VMI: namely, inventory, transportation, manufacturing, general benefits, coordination/collaboration, and information sharing. In addition, there are, three methodological classifications: modelling, simulation, and case studies. Finally, we will consider...

Scenarios for potential radionuclide release from marine reactors dumped in the Kara Sea

International Nuclear Information System (INIS)

Lynn, N.; Mount, M.; Gussgard, K.

1995-01-01

The largest inventory of radioactive materials dumped in the Kara Sea by the former Soviet Union comes from the spent nuclear fuel (SNF) of seven marine reactors, the current (1994) inventory of which makes a total of approximately 4.7x10 15 Bq. In progressing its work for the International Arctic Seas Assessment Project, under the auspices of the International Atomic Energy Agency, the Source Term Working Group has analysed the Source Term and subsequently developed a number of model scenarios for the potential release patterns of radionuclides into the Kara Sea from the SNF and activated components dumped within the marine reactors.These models are based on the present and future conditions of the barrier materials and their configuration within the dumped objects. They account for progressive corrosion of the outer and inner steel barriers, breakdown of the organic fillers, and degradation and leaching from the SNFs. Annual release rates are predicted to four thousand years into the future. 5 refs., 1 fig., 1 tab

Housing Inventory Count

Data.gov (United States)

Department of Housing and Urban Development — This report displays the data communities reported to HUD about the nature of their dedicated homeless inventory, referred to as their Housing Inventory Count (HIC)....

27 CFR 40.201 - Inventories.

Science.gov (United States)

2010-04-01

... PROCESSED TOBACCO Operations by Manufacturers of Tobacco Products Inventories and Reports § 40.201 Inventories. Every manufacturer of tobacco products shall make true and accurate inventories on Form 5210.9... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Inventories. 40.201...

Use of ELOCA.Mk5 to calculate transient fission product release from CANDU fuel elements

International Nuclear Information System (INIS)

Walker, J.R.; de Vaal, J.W.; Arimescu, V.I.; McGrady, T.G.; Wong, C.

1992-04-01

A change in fuel element power output, or a change in heat transfer conditions, will result in an immediate change in the temperature distribution in a fuel element. The temperature distribution change will be accompanied by concomitant changes in fuel stress distribution that lead, in turn, to a release of fission products to the fuel-to-sheath gap. It is important to know the inventory of fission products in the fuel-to-sheath gap, because this inventory is a major component of the source term for many postulated reactor accidents. ELOCA.Mk5 is a FORTRAN-77 computer code that has been developed to estimate transient releases to the fuel-to-sheath gap in CANDU reactors. ELOCA.Mk5 is an integration of the FREEDOM fission product release model into the ELOCA fuel element thermo-mechanical code. The integration of FREEDOM into ELOCA allows ELOCA.Mk5 to model the feedback mechanisms between the fission product release and the thermo-mechanical response of the fuel element. This paper describes the physical model, gives details of the ELOCA.Mkt code, and describes the validation of the model. We demonstrate that the model gives good agreement with experimental results for both steady state and transient conditions

Spare Parts Inventory Management for the Next Generation Finnish Defense Force Fighter Fleet

Science.gov (United States)

2017-12-01

might benefit the end user most in high criticality or high cost classification classes: CrA, CrB, EA and EB. H. LEAD TIME EFFECTS Lead time is...NAVAL POSTGRADUATE SCHOOL MONTEREY, CALIFORNIA THESIS Approved for public release. Distribution is unlimited. SPARE PARTS INVENTORY MANAGEMENT...Eddine Dahel THIS PAGE INTENTIONALLY LEFT BLANK i REPORT DOCUMENTATION PAGE Form Approved OMB No. 0704–0188 Public reporting burden for this collection

Center for Integrated Nanotechnologies (CINT) Chemical Release Modeling Evaluation

Energy Technology Data Exchange (ETDEWEB)

Stirrup, Timothy Scott [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-12-20

This evaluation documents the methodology and results of chemical release modeling for operations at Building 518, Center for Integrated Nanotechnologies (CINT) Core Facility. This evaluation is intended to supplement an update to the CINT [Standalone] Hazards Analysis (SHA). This evaluation also updates the original [Design] Hazards Analysis (DHA) completed in 2003 during the design and construction of the facility; since the original DHA, additional toxic materials have been evaluated and modeled to confirm the continued low hazard classification of the CINT facility and operations. This evaluation addresses the potential catastrophic release of the current inventory of toxic chemicals at Building 518 based on a standard query in the Chemical Information System (CIS).

Functional Assessment Inventory Manual.

Science.gov (United States)

Crewe, Nancy M.; Athelstan, Gary T.

This manual, which provides extensive new instructions for administering the Functional Assessment Inventory (FAI), is intended to enable counselors to begin using the inventory without undergoing any special training. The first two sections deal with the need for functional assessment and issues in the development and use of the inventory. The…

ICPP water inventory study project summary report

International Nuclear Information System (INIS)

Richards, B.T.

1994-01-01

The Idaho Chemical Processing Plant (ICPP) Water inventory Study was initiated in September 1993 with the formation of a joint working group consisting of representatives from DOE-ID, State of Idaho INEL Oversight Program, US Geological Survey, and INEL employees to investigate three issues that had been identified by the INEL Oversight Program at ICPP: (1) the water inventory imbalance at ICPP, (2) the source of water infiltrating into the Tank Farm vault sumps, and (3) the source of water providing potential recharge to perched water bodies underlying ICPP. These issues suggested that water was being lost from the ICPP distribution system. The INEL Oversight Program was concerned that the unaccounted for water at ICPP could be spreading contaminants that have been released over the past 40 years of operations of ICPP, possibly to the Snake River Plain Aquifer. This report summarizes the findings of each of the component investigations that were undertaken to resolve each of the three issues. Concerns about the risk of spreading contaminants will be resolved as part of the Remedial Investigation/Feasibility Study being undertaken at ICPP in compliance with the Federal Facility Agreement and Consent Order between DOE-H), EPA, and the State of Idaho. This report will be a key input to that study

Release of chlorine from biomass at gasification conditions

Energy Technology Data Exchange (ETDEWEB)

Bjoerkman, E.; Stroemberg, B. [TPS Termiska Processer AB, Nykoeping (Sweden)

1997-05-01

The objective of the project was to investigate the influence of different gasifying atmospheres on the release of chlorine from biomass during gasification conditions. Furthermore, the purpose was also to try and identify the formed chloro compounds. The results showed that O{sub 2}, H{sub 2}O and CO{sub 2} had negligible effect on the chlorine release at temperatures under 700 deg C. At temperatures above 800 deg C the reactivity towards CO{sub 2} increased and could be seen as higher chlorine release and less solid residue. No chloro organic compounds (aliphatic one to six carbons or aromatic one to two rings) could be detected in the tar or the fuel gas produced during pyrolysis/gasifying. On the other hand, comparable amounts of chlorinated benzenes were found in the cooling section during combustion of lucerne and of synthetic waste, indicating that oxygen is essential for chlorination reactions. 11 refs, 4 figs, 1 tab

Release of chlorine from biomass at gasification conditions

International Nuclear Information System (INIS)

Bjoerkman, E.; Stroemberg, B.

1997-05-01

The objective of the project was to investigate the influence of different gasifying atmospheres on the release of chlorine from biomass during gasification conditions. Furthermore, the purpose was also to try and identify the formed chloro compounds. The results showed that O 2 , H 2 O and CO 2 had negligible effect on the chlorine release at temperatures under 700 deg C. At temperatures above 800 deg C the reactivity towards CO 2 increased and could be seen as higher chlorine release and less solid residue. No chloro organic compounds (aliphatic one to six carbons or aromatic one to two rings) could be detected in the tar or the fuel gas produced during pyrolysis/gasifying. On the other hand, comparable amounts of chlorinated benzenes were found in the cooling section during combustion of lucerne and of synthetic waste, indicating that oxygen is essential for chlorination reactions. 11 refs, 4 figs, 1 tab

Optimal fuel inventory strategies

International Nuclear Information System (INIS)

Caspary, P.J.; Hollibaugh, J.B.; Licklider, P.L.; Patel, K.P.

1990-01-01

In an effort to maintain their competitive edge, most utilities are reevaluating many of their conventional practices and policies in an effort to further minimize customer revenue requirements without sacrificing system reliability. Over the past several years, Illinois Power has been rethinking its traditional fuel inventory strategies, recognizing that coal supplies are competitive and plentiful and that carrying charges on inventory are expensive. To help the Company achieve one of its strategic corporate goals, an optimal fuel inventory study was performed for its five major coal-fired generating stations. The purpose of this paper is to briefly describe Illinois Power's system and past practices concerning coal inventories, highlight the analytical process behind the optimal fuel inventory study, and discuss some of the recent experiences affecting coal deliveries and economic dispatch

Tri-maximal vs. bi-maximal neutrino mixing

International Nuclear Information System (INIS)

Scott, W.G

2000-01-01

It is argued that data from atmospheric and solar neutrino experiments point strongly to tri-maximal or bi-maximal lepton mixing. While ('optimised') bi-maximal mixing gives an excellent a posteriori fit to the data, tri-maximal mixing is an a priori hypothesis, which is not excluded, taking account of terrestrial matter effects

Release Strategies: The CMS approach for Development and Quality Assurance

International Nuclear Information System (INIS)

Sexton-Kennedy, Elizabeth

2011-01-01

Now that CMS has started data taking there is a balance to be struck between software release stability for operations and the need to improve the physics and technical performance of the code. In addition new code may need to be developed to correct for unforeseen data taking conditions, and has to be integrated into the mainstream releases with a minimum risk. To keep the process under control, CMS uses regular (twice a day) Integration Builds. A complex set of validation steps is used to verify the software at various stages, from the regular Integration Builds to running a full software and physics validation suite on the grid for major releases. CMS has adopted a development model that tries to strike the correct balance between the needs of stability and a constant improvement; this paper will describe our experience with this model, and tell the story of how the commissioning of the CMS offline has proceeded through the perspective of the past year's releases.

A Transgenic Tri-Modality Reporter Mouse

OpenAIRE

Yan, Xinrui; Ray, Pritha; Paulmurugan, Ramasamy; Tong, Ricky; Gong, Yongquan; Sathirachinda, Ataya; Wu, Joseph C.; Gambhir, Sanjiv S.

2013-01-01

Transgenic mouse with a stably integrated reporter gene(s) can be a valuable resource for obtaining uniformly labeled stem cells, tissues, and organs for various applications. We have generated a transgenic mouse model that ubiquitously expresses a tri-fusion reporter gene (fluc2-tdTomato-ttk) driven by a constitutive chicken β-actin promoter. This "Tri-Modality Reporter Mouse" system allows one to isolate most cells from this donor mouse and image them for bioluminescent (fluc2), fluorescent...

A single-item inventory model for expected inventory order crossovers

NARCIS (Netherlands)

Riezebos, J.; Gaalman, G.J.C.

2009-01-01

Expected inventory order crossovers Occur if at the moment of ordering it is expected that orders will not arrive in the sequence they are ordered. Recent research has shown that (it) expected inventory order crossovers will be encountered more frequently in future, and that (b) use of a myopic

Controlling Inventory: Real-World Mathematical Modeling

Science.gov (United States)

Edwards, Thomas G.; Özgün-Koca, S. Asli; Chelst, Kenneth R.

2013-01-01

Amazon, Walmart, and other large-scale retailers owe their success partly to efficient inventory management. For such firms, holding too little inventory risks losing sales, whereas holding idle inventory wastes money. Therefore profits hinge on the inventory level chosen. In this activity, students investigate a simplified inventory-control…

[Inventories of atmospheric arsenic emissions from coal combustion in China, 2005].

Science.gov (United States)

Tian, He-Zhong; Qu, Yi-Ping

2009-04-15

Anthropogenic arsenic (As) emitted from coal combustion is one of key trace elements leading to negative air pollution and national economy loss. It is of great significance to estimate the atmospheric arsenic emission for proposing relevant laws or regulations and selecting proper pollution control technologies. The inventories of atmospheric arsenic emissions from coal combustion in China were evaluated by adopting the emission factor method based on fuel consumption. Arsenic emission sources were firstly classified into several categories by economic sectors, combustion types and pollution control technologies. Then, according to provincial coal consumption and averaged arsenic concentration in the feed fuel, the inventories of atmospheric arsenic emission from coal combustion in China in 2005 were established. Coal outputand consumption in China in 2005 were 2,119.8 and 2,099.8 Mt, respectively. The total emissions of arsenic released into the atmosphere in 2005 in China were estimated at about 1,564.4 t, and Shandong ranked the largest province with 144.4 t arsenic release, followed by Hunan (141.1 t), Hebei (108.5 t), Henan (77.7 t), and Jiangsu (77.0 t), which were mainly concentrated in the eastern and central provinces of China. The arsenic emissions were largely emitted by industry sector (818.8 t) and thermal power generation sector (303.4 t), contributing 52.3% and 19.4% of the totals, respectively. About 375.5 t arsenic was estimated to be released into the atmosphere in the form of gas phase in China in 2005, with a share of 24% of the totals. In general, arsenic pollution control from coal combustion should be highlighted for the power and industry sectors in the whole country. However, arsenic poisoning caused by residential coal burning should also be paid great attention in some areas such as Xinjiang, Gansu, Qinghai and Guishou.

21 CFR 1304.11 - Inventory requirements.

Science.gov (United States)

2010-04-01

... the inventory of the registered location to which they are subject to control or to which the person... 21 Food and Drugs 9 2010-04-01 2010-04-01 false Inventory requirements. 1304.11 Section 1304.11... REGISTRANTS Inventory Requirements § 1304.11 Inventory requirements. (a) General requirements. Each inventory...

Update and improvement of the global krypton-85 emission inventory.

Science.gov (United States)

Ahlswede, Jochen; Hebel, Simon; Ross, J Ole; Schoetter, Robert; Kalinowski, Martin B

2013-01-01

Krypton-85 is mainly produced in nuclear reactors by fission of uranium and plutonium and released during chopping and dissolution of spent fuel rods in nuclear reprocessing facilities. As noble gas it is suited as a passive tracer for evaluation of atmospheric transport models. Furthermore, research is ongoing to assess its quality as an indicator for clandestine reprocessing activities. This paper continues previous efforts to compile a comprehensive historic emission inventory for krypton-85. Reprocessing facilities are the by far largest emitters of krypton-85. Information on sources and calculations used to derive the annual krypton-85 emission is provided for all known reprocessing facilities in the world. In addition, the emission characteristics of two plants, Tokai (Japan) and La Hague (France), are analysed in detail using emission data with high temporal resolution. Other types of krypton-85 sources are power reactors, naval reactors and isotope production facilities. These sources contribute only little or negligible amounts of krypton-85 compared to the large reprocessing facilities. Taking the decay of krypton-85 into account, the global atmospheric inventory is estimated to about 5500 PBq at the end of 2009. The correctness if the inventory has been proven by meteorological simulations and its error is assumed to be in the range of a few percent. Copyright © 2012 Elsevier Ltd. All rights reserved.

The cytosolic chaperonin CCT/TRiC and cancer cell proliferation.

Directory of Open Access Journals (Sweden)

Chafika Boudiaf-Benmammar

Full Text Available The molecular chaperone CCT/TRiC plays a central role in maintaining cellular proteostasis as it mediates the folding of the major cytoskeletal proteins tubulins and actins. CCT/TRiC is also involved in the oncoprotein cyclin E, the Von Hippel-Lindau tumour suppressor protein, cyclin B and p21(ras folding which strongly suggests that it is involved in cell proliferation and tumor genesis. To assess the involvement of CCT/TRiC in tumor genesis, we quantified its expression levels and activity in 18 cancer, one non-cancer human cell lines and a non-cancer human liver. We show that the expression levels of CCT/TRiC in cancer cell lines are higher than that in normal cells. However, CCT/TRiC activity does not always correlate with its expression levels. We therefore documented the expression levels of CCT/TRiC modulators and partners PhLP3, Hop/P60, prefoldin and Hsc/Hsp70. Our analysis reveals a functional interplay between molecular chaperones that might account for a precise modulation of CCT/TRiC activity in cell proliferation through changes in the cellular levels of prefoldin and/or Hsc/p70 and CCT/TRiC client protein availability. Our observation and approaches bring novel insights in the role of CCT/TRiC-mediated protein folding machinery in cancer cell development.

Fission-product release modelling in the ASTEC integral code: the status of the ELSA module

International Nuclear Information System (INIS)

Plumecocq, W.; Kissane, M.P.; Manenc, H.; Giordano, P.

2003-01-01

Safety assessment of water-cooled nuclear reactors encompasses potential severe accidents where, in particular, the release of fission products (FPs) and actinides into the reactor coolant system (RCS) is evaluated. The ELSA module is used in the ASTEC integral code to model all releases into the RCS. A wide variety of experiments is used for validation: small-scale CRL, ORNL and VERCORS tests; large-scale Phebus-FP tests; etc. Being a tool that covers intact fuel and degraded states, ELSA is being improved maximizing the use of information from degradation modelling. Short-term improvements will include some treatment of initial FP release due to intergranular inventories and implementing models for release of additional structural materials (Sn, Fe, etc.). (author)

Exhausted Parents: Development and Preliminary Validation of the Parental Burnout Inventory

Directory of Open Access Journals (Sweden)

Isabelle Roskam

2017-02-01

Full Text Available Can parents burn out? The aim of this research was to examine the construct validity of the concept of parental burnout and to provide researchers which an instrument to measure it. We conducted two successive questionnaire-based online studies, the first with a community-sample of 379 parents using principal component analyses and the second with a community- sample of 1,723 parents using both principal component analyses and confirmatory factor analyses. We investigated whether the tridimensional structure of the burnout syndrome (i.e., exhaustion, inefficacy, and depersonalization held in the parental context. We then examined the specificity of parental burnout vis-à-vis professional burnout assessed with the Maslach Burnout Inventory, parental stress assessed with the Parental Stress Questionnaire and depression assessed with the Beck Depression Inventory. The results support the validity of a tri-dimensional burnout syndrome including exhaustion, inefficacy and emotional distancing with, respectively, 53.96 and 55.76% variance explained in study 1 and study 2, and reliability ranging from 0.89 to 0.94. The final version of the Parental Burnout Inventory (PBI consists of 22 items and displays strong psychometric properties (CFI = 0.95, RMSEA = 0.06. Low to moderate correlations between parental burnout and professional burnout, parental stress and depression suggests that parental burnout is not just burnout, stress or depression. The prevalence of parental burnout confirms that some parents are so exhausted that the term “burnout” is appropriate. The proportion of burnout parents lies somewhere between 2 and 12%. The results are discussed in light of their implications at the micro-, meso- and macro-levels.

Exhausted Parents: Development and Preliminary Validation of the Parental Burnout Inventory

Science.gov (United States)

Roskam, Isabelle; Raes, Marie-Emilie; Mikolajczak, Moïra

2017-01-01

Can parents burn out? The aim of this research was to examine the construct validity of the concept of parental burnout and to provide researchers which an instrument to measure it. We conducted two successive questionnaire-based online studies, the first with a community-sample of 379 parents using principal component analyses and the second with a community- sample of 1,723 parents using both principal component analyses and confirmatory factor analyses. We investigated whether the tridimensional structure of the burnout syndrome (i.e., exhaustion, inefficacy, and depersonalization) held in the parental context. We then examined the specificity of parental burnout vis-à-vis professional burnout assessed with the Maslach Burnout Inventory, parental stress assessed with the Parental Stress Questionnaire and depression assessed with the Beck Depression Inventory. The results support the validity of a tri-dimensional burnout syndrome including exhaustion, inefficacy and emotional distancing with, respectively, 53.96 and 55.76% variance explained in study 1 and study 2, and reliability ranging from 0.89 to 0.94. The final version of the Parental Burnout Inventory (PBI) consists of 22 items and displays strong psychometric properties (CFI = 0.95, RMSEA = 0.06). Low to moderate correlations between parental burnout and professional burnout, parental stress and depression suggests that parental burnout is not just burnout, stress or depression. The prevalence of parental burnout confirms that some parents are so exhausted that the term “burnout” is appropriate. The proportion of burnout parents lies somewhere between 2 and 12%. The results are discussed in light of their implications at the micro-, meso- and macro-levels. PMID:28232811

Crystal structures of fac-tri?chlorido?tris?(tri?methyl?phosphane-?P)rhodium(III) monohydrate and fac-tri?chlorido?tris?(tri?methyl?phosphane-?P)rhodium(III) methanol hemisolvate: rhodium structures that are isotypic with their iridium analogs

OpenAIRE

Merola, Joseph S.; Franks, Marion A.

2015-01-01

The crystal structures of two solvates of fac-tri-chlorido-tris-(tri-methyl-phosphane-κP)rhodium(III) are reported, i.e. one with water in the crystal lattice, fac-[RhCl3(Me3P)3]·H2O, and one with methanol in the crystal lattice, fac-[RhCl3(Me3P)3]·0.5CH3OH. These rhodium compounds exhibit distorted octahedral coordination spheres at the metal and are isotypic with the analogous iridium compounds previously reported by us [Merola et al. (2013 ▶). Polyhedron, 54, 67-73]. Comparison is made bet...

Brief pain inventory scale: An emerging assessment modality for orofacial pain

Directory of Open Access Journals (Sweden)

Ruchika Khanna

2015-01-01

Full Text Available Pain is an emotional experience almost experienced by almost every one of us. Since the pain can neither be seen nor measured, it poses a challenge to the patient as well as the clinician in understanding its complicated nature and the best way of managing it. There is no simple method of pain evaluation due to its subjective nature. However, comprehensive approaches for its evaluation exists, of which most common pain scale used are visual analog scale, Mc-Gills questionnaire, brief pain inventory (BPI to name a few. We have tried to highlight the various advantages of the BPI scale over the other pain scales and to emphasize an improved instrument, which can be used as a promising modality for the assessment of orofacial pain.

Procedure for taking physical inventories

International Nuclear Information System (INIS)

Boston, R.A.

1984-01-01

Physical inventories are taken periodically to meet Company, State and IAEA requirements. Those physical inventories may be verified by IAEA and/or State inspectors. This presentation describes in an introductory but detailed manner the approaches and procedures used in planning, preparing, conducting, reconciling and reporting physical inventories for the Model Plant. Physical inventories are taken for plant accounting purposes to provide an accurate basis for starting and closing the plant material balance. Physical inventories are also taken for safeguards purposes to provide positive assurance that the nuclear materials of concern are indeed present and accounted for

Fukushima - calculation of the reactor core inventory and storage pools Dai-ichi 1 to Dai-ichi 4, an estimation of a source term

International Nuclear Information System (INIS)

Krpelanova, M.; Carny, P.

2011-01-01

Inventory of the reactor core and spent fuel storage pool of the reactors at Dai-ichi 1 to Dai-ichi 4 was determined to need a realistic estimate of the source (released into the atmosphere environment) and modelling of radiological impact of the events in Fukushima NPP. Calculations of inventories were carried out by the methodology that is used in systems to support emergency response and crisis management anymore. Calculations were made based on a model that respects knowledge of real fuels and fuel cycles for individual reactors Dai-ichi. Necessary input data for training the model and calculate inventories are obtained from the IAEA PRIS database.

Radionuclide release calculations for SAR-08

International Nuclear Information System (INIS)

Thomson, Gavin; Miller, Alex; Smith, Graham; Jackson, Duncan

2008-04-01

Following a review by the Swedish regulatory authorities of the post-closure safety assessment of the SFR 1 disposal facility for low and intermediate waste (L/ILW), SAFE, the SKB has prepared an updated assessment called SAR-08. This report describes the radionuclide release calculations that have been undertaken as part of SAR-08. The information, assumptions and data used in the calculations are reported and the results are presented. The calculations address issues raised in the regulatory review, but also take account of new information including revised inventory data. The scenarios considered include the main case of expected behaviour of the system, with variants; low probability releases, and so-called residual scenarios. Apart from these scenario uncertainties, data uncertainties have been examined using a probabilistic approach. Calculations have been made using the AMBER software. This allows all the component features of the assessment model to be included in one place. AMBER has been previously used to reproduce results the corresponding calculations in the SAFE assessment. It is also used in demonstration of the IAEA's near surface disposal assessment methodology ISAM and has been subject to very substantial verification tests and has been used in verifying other assessment codes. Results are presented as a function of time for the release of radionuclides from the near field, and then from the far field into the biosphere. Radiological impacts of the releases are reported elsewhere. Consideration is given to each radionuclide and to each component part of the repository. The releases from the entire repository are also presented. The peak releases rates are, for most scenarios, due to organic C-14. Other radionuclides which contribute to peak release rates include inorganic C-14, Ni-59 and Ni-63. (author)

Radionuclide release calculations for SAR-08

Energy Technology Data Exchange (ETDEWEB)

Thomson, Gavin; Miller, Alex; Smith, Graham; Jackson, Duncan (Enviros Consulting Ltd, Wolverhampton (United Kingdom))

2008-04-15

Following a review by the Swedish regulatory authorities of the post-closure safety assessment of the SFR 1 disposal facility for low and intermediate waste (L/ILW), SAFE, the SKB has prepared an updated assessment called SAR-08. This report describes the radionuclide release calculations that have been undertaken as part of SAR-08. The information, assumptions and data used in the calculations are reported and the results are presented. The calculations address issues raised in the regulatory review, but also take account of new information including revised inventory data. The scenarios considered include the main case of expected behaviour of the system, with variants; low probability releases, and so-called residual scenarios. Apart from these scenario uncertainties, data uncertainties have been examined using a probabilistic approach. Calculations have been made using the AMBER software. This allows all the component features of the assessment model to be included in one place. AMBER has been previously used to reproduce results the corresponding calculations in the SAFE assessment. It is also used in demonstration of the IAEA's near surface disposal assessment methodology ISAM and has been subject to very substantial verification tests and has been used in verifying other assessment codes. Results are presented as a function of time for the release of radionuclides from the near field, and then from the far field into the biosphere. Radiological impacts of the releases are reported elsewhere. Consideration is given to each radionuclide and to each component part of the repository. The releases from the entire repository are also presented. The peak releases rates are, for most scenarios, due to organic C-14. Other radionuclides which contribute to peak release rates include inorganic C-14, Ni-59 and Ni-63. (author)

Initial Analysis of VOCs Speciation in CREATE Emissions Inventory using the MAPS-Seoul Aircraft Field Campaign

Science.gov (United States)

Bu, C.; Woo, J. H.; Lee, Y.; Kim, J.; Choi, K. C.; Kim, Y.; Kim, J.; Jang, Y. K.; Kim, S.

2016-12-01

As the first international cooperative air quality field study, the MAPS-Seoul (Megacity Air Pollution Studies-Seoul) aircraft mission was conducted in May - June 2016 over the South Korea, to understand of climate and atmospheric environment. The aircraft carried observation instruments for measurements of GHGs, ozone and its precursors, aerosols, and chemical tracers. The CREATE (Comprehensive Regional Emissions inventory for Atmospheric Environment) emissions inventory and SMOKE-Asia emission processing system were used to support chemical forecasting and to serve as a priori for evaluation. Initial results of comparison studies show large discrepancies in VOC species over the South Korea - especially over urban regions. Several VOC species observed high near megacities and petro-chemical plants but under-predicted by chemical transport models (CTMs) - possibly due to relatively low emissions. The chemical speciation profiles and emissions inventory for each emission sources, therefore, have to be re-visited to improve emissions information. In this study, we have; 1) re-examined our emissions inventory and emission speciation processes, 2) and tried to find possible missing sources and alternative chemical speciation profiles, to improve our modelling emissions inventory. Initial review of the mapping and classification profiles, the original US chemical speciation profiles were found to be low in partitioning painting and surface coating sources, although they are the very significant contributors. Unlike other major national cities in China, Shanghai's VOC emissions fraction seems very similar to that of Seoul. Continuous analysis of major urban and industrial areas of the country will be presented at site.Acknowledgements : This subject is supported by Korea Ministry of Environment as "Climate Change Correspondence Program". This work was supported by a grant from the National Institute of Environment Research (NIER), funded by the Ministry of Environment

Mercury emissions inventory for 2014 in Costa Rica using the PNUMA Toolkit to a N2 level

Directory of Open Access Journals (Sweden)

Julio César Murillo-Hernández

2017-12-01

Full Text Available The Minamata Convention was signed in October 2013 to protect human health and the environment from releases and anthropogenic emissions of elemental mercury and compounds containing this element.  When Costa Rica ratified this instrument, the country committed to develop and keep updated an inventory of emissions from the relevant sources of mercury. In the present work, the tool proposed by UNEP was used to generate the first mercury inventory at the N2 level of the country, which considers releases of mercury in air, water, soil, product and waste matrices. Taking 2014 as the reference year, the estimated mercury emission for Costa Rica was recorded at 5 052 kg, with an uncertainty interval between 2 675 kg and 10 525 kg; and the most important sectors in terms of the total emission were the extraction of gold with amalgamation (42 %, informal burning of waste (15 % and use of dental amalgams (10 %. The most impacted matrices were air (29 %, water (28 % and soil (21 %, respectively.

Initial Radionuclide Inventories

Energy Technology Data Exchange (ETDEWEB)

H. Miller

2004-09-19

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement

Validation of Schema Coping Inventory and Schema Mode Inventory in Adolescents

NARCIS (Netherlands)

van Wijk-Herbrink, M.F.; Roelofs, J.; Broers, N.J.; Rijkeboer, M.M.; Arntz, A.; Bernstein, D.P.

2018-01-01

This study investigated whether the schema therapy constructs of schema coping and schema modes have validity in adolescents. We examined the validity and reliability of the Schema Coping Inventory (SCI) and an 80-item version of the Schema Mode Inventory (SMI) in a mixed sample of adolescents.

Influence of start up and pulsed operation on tritium release and inventory of NET ceramic blanket

International Nuclear Information System (INIS)

Iseli, M.; Esser, B.

1989-01-01

A first estimate for the tritium release behaviour of a ceramic breeder blanket in pulsed operation is obtained by assuming a linear steady state temperature distribution and taking into account the time constant of the thermal behaviour. The release behaviour of the breeder exposed to consecutive periods of tritium generation is described with an analytical solution of the diffusion equation. The results are compared with a simple exponential approach valid for surfacte desorption controlled release. The exponential model is used to simulate a blanket with aluminate as breeder material, which takes longest to reach steady state. The simulation demonstrates that a significant fraction (>67%) of steady state can be achieved after a testing time of about one day. (author). 7 refs.; 8 figs.; 3 tabs

On Inventory Control For Perishable Inventory Systems Subject To Uncertainties On Customer Demands

OpenAIRE

Abbou , Rosa; Loiseau , Jean-Jacques; Khaldi , Hajer; Farraa , Berna ,

2017-01-01

International audience; This paper deals with the inventory controller design for constrained production systems subject to uncertainties on the customer demands. The case study focuses on the inventory regulation problem in production systems where contain perishable finite products. Such systems are characterized by the presence of delays due to production processes, and constraints from the instantaneous inventory level, production level and the finite capacities of stocks. To do that, we ...

In-pile test of tritium release from tritium breeding materials (VOM-21H experiment)

International Nuclear Information System (INIS)

Kurasawa, Toshimasa; Takeshita, Hidefumi; Watanabe, Hitoshi; Yoshida, Hiroshi.

1986-10-01

Material development and blanket design of lithium-based ceramics such as lithium oxide, lithium aluminate, lithium silicate and lithium zirconate have been performed in Japan, United State of America and Europian Communities. Lithium oxide is a most attractive candidate for tritium breeding materials because of its high lithium density, high thermal conductivity and good tritium release performance. This work has been done to clarify the characteristics of tritium release and recovery from Li 2 O by means of in-situ tritium release measurement. The effects of temperature and sweep gas composition on the tritium release were investigated in this VOM-21H Experiment. Good measurement of tritium release was achieved but there were uncertainties in reproduciblity of data. The experimental results show that the role of surface adsorption/desorption makes a significant contribution to the tritium release and tritium inventory. Also, it is necessary to define the rate limiting process either diffusion or surface adsorption/desorption. (author)

Denmark's National Inventory Report 2010

DEFF Research Database (Denmark)

Nielsen, Ole-Kenneth; Lyck, Erik; Mikkelsen, Mette Hjorth

2010-01-01

This report is Denmark's National Inventory Report 2010. The report contains information on Denmark's emission inventories for all years' from 1990 to 2008 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2.......This report is Denmark's National Inventory Report 2010. The report contains information on Denmark's emission inventories for all years' from 1990 to 2008 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2....

Migration of di- and tri-interstitials in silicon

International Nuclear Information System (INIS)

Posselt, M.; Gao, F.; Zwicker, D.

2005-01-01

A comprehensive study on the migration of di- and tri-interstitials in silicon is performed using classical molecular dynamics simulations with the Stillinger-Weber potential. The initial di- and tri-interstitial configurations with the lowest formation energies are determined, and then, the defect migration is investigated for temperatures between 800 and 1600 K. The defect diffusivity and the self-diffusion coefficient per defect are calculated. Compared to the mono-interstitial, the di-interstitial migrates faster, whereas the tri-interstitial diffuses slower. The migration mechanism of the di-interstitial shows a pronounced dependence on the temperature. Like in the case of the mono-interstitial, the mobility of the di-interstitial is higher than the mobility of the lattice atoms during the defect diffusion. On the other hand, the tri-interstitial mobility is lower than the corresponding atomic mobility. The implications of the present results for the analysis of experimental data on defect evolution and migration are discussed

Environmental Effects on the Polypyrrole Tri-layer Actuator

Directory of Open Access Journals (Sweden)

Nirul Masurkar

2017-04-01

Full Text Available Electroactive polymer actuators such as polypyrrole (PPy are exciting candidates to drive autonomous devices that require low weight and low power. A simple PPy tri-layer bending type cantilever which operates in the air has been demonstrated previously, but the environmental effect on this actuator is still unknown. The major obstacle in the development of the PPy tri-layer actuator is to create proper packaging that reduces oxidation of the electrolyte and maintains constant displacement. Here, we report the variation in the displacement as well as the charge transfer at the different environmental condition. PPy trilayer actuators were fabricated by depositing polypyrrole on gold-coated porous poly(vinylidene fluoride (PVDF using the electro-synthesis method. It has been demonstrated that the charge transfer of tri-layer actuators is more in an inert environment than in open air. In addition, tri-layer actuators show constant deflection and enhancement of life due to the negligible oxidation rate of the electrolyte in an inert environment.

HHS Enterprise Data Inventory

Data.gov (United States)

U.S. Department of Health & Human Services — The Enterprise Data Inventory (EDI) is the comprehensive inventory listing of agency data resources including public, restricted public, and non-public datasets.

27 CFR 20.170 - Physical inventory.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Physical inventory. 20.170... Users of Specially Denatured Spirits Inventory and Records § 20.170 Physical inventory. Once in each... physical inventory of each formula of new and recovered specially denatured spirits. (Approved by the...

Endogenous Business Cycle Dynamics within Metzlers Inventory Model: Adding an Inventory Floor.

Science.gov (United States)

Sushko, Irina; Wegener, Michael; Westerhoff, Frank; Zaklan, Georg

2009-04-01

Metzlers inventory model may produce dampened fluctuations in economic activity, thus contributing to our understanding of business cycle dynamics. For some parameter combinations, however, the model generates oscillations with increasing amplitude, implying that the inventory stock of firms eventually turns negative. Taking this observation into account, we reformulate Metzlers model by simply putting a floor to the inventory level. Within the new piecewise linear model, endogenous business cycle dynamics may now be triggered via a center bifurcation, i.e. for certain parameter combinations production changes are (quasi-)periodic.

Savannah River Plant's Accountability Inventory Management System (AIMS) (Nuclear materials inventory control)

International Nuclear Information System (INIS)

Croom, R.G.

1976-06-01

The Accountability Inventory Management System (AIMS) is a new computer inventory control system for nuclear materials at the Savannah River Plant, Aiken, South Carolina. The system has two major components, inventory files and system parameter files. AIMS, part of the overall safeguards program, maintains an up-to-date record of nuclear material by location, produces reports required by ERDA in addition to onplant reports, and is capable of a wide range of response to changing input/output requirements through use of user-prepared parameter cards, as opposed to basic system reprogramming

27 CFR 40.523 - Inventories.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Inventories. 40.523... PROCESSED TOBACCO Manufacture of Processed Tobacco Operations by Manufacturers of Processed Tobacco § 40.523 Inventories. Every manufacturer of processed tobacco must provide a true and accurate inventory on TTB F 5210...

Hydrogen inventory in gallium

International Nuclear Information System (INIS)

Mazayev, S.N.; Prokofiev, Yu.G.

1994-01-01

Investigations of hydrogen inventory in gallium (99.9%) were carried out after saturation both from molecular phase and from glow discharge plasma at room temperature, 370 and 520 K. Saturation took place during 3000 s under hydrogen pressure of 20 Pa, and ion flux was about 1x10 15 ions/cm 2 s with an energy about 400 eV during discharge. Hydrogen concentration in Ga at room temperature and that for 370 K by the saturation from gaseous phase was (2-3)x10 14 cm -3 Pa -1/2 . Hydrogen concentration at temperature 520 K increased by five times. Inventory at room temperature for irradiation from discharge was 7x10 16 cm -3 at the dose about 3x10 18 ions/cm 2 . It was more than inventory at temperature 520 K by four times and more than maximum inventory from gaseous phase at 520 K by a factor of 10. Inventory increased when temperature decreased. Diffusion coefficient D=0.003 exp(-2300/RT) cm 2 /s, was estimated from temperature dependence. ((orig.))

Nuclear materials inventory plan

International Nuclear Information System (INIS)

Doerr, R.W.; Nichols, D.H.

1982-03-01

In any processing, manufacturing, or active storage facility it is impractical to assume that any physical security system can prevent the diversion of Special Nuclear Material (SNM). It is, therefore, the responsibility of any DOE Contractor, Licensee, or other holder of SNM to provide assurance that loss or diversion of a significant quantity of SNM is detectable. This ability to detect must be accomplishable within a reasonable time interval and can be accomplished only by taking physical inventories. The information gained and decisions resulting from these inventories can be no better than the SNM accounting system and the quality of measurements performed for each receipt, removal and inventory. Inventories interrupt processing or production operations, increase personnel exposures, and can add significantly to the cost of any operation. Therefore, realistic goals for the inventory must be defined and the relationship of the inherent parameters used in its validation be determined. Purpose of this document is to provide a statement of goals and a plan of action to achieve them

Denmark's National Inventory Report 2014

DEFF Research Database (Denmark)

Nielsen, Ole-Kenneth; Plejdrup, Marlene Schmidt; Winther, Morten

This report is Denmark’s National Inventory Report 2014. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2012 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2......This report is Denmark’s National Inventory Report 2014. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2012 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2...

Denmark's National Inventory Report 2013

DEFF Research Database (Denmark)

Nielsen, Ole-Kenneth; Plejdrup, Marlene Schmidt; Winther, Morten

This report is Denmark’s National Inventory Report 2013. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2011 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2.......This report is Denmark’s National Inventory Report 2013. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2011 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2....

Denmark's National Inventory Report 2017

DEFF Research Database (Denmark)

Nielsen, Ole-Kenneth; Plejdrup, Marlene Schmidt; Winther, Morten

This report is Denmark’s National Inventory Report 2017. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2015 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2......This report is Denmark’s National Inventory Report 2017. The report contains information on Denmark’s emission inventories for all years’ from 1990 to 2015 for CO2, CH4, N2O, HFCs, PFCs and SF6, NOx, CO, NMVOC, SO2...

Six ways to reduce inventory.

Science.gov (United States)

Lunn, T

1996-05-01

The purpose of this presentation is to help you reduce the inventory in your operation. We will accomplish that task by discussing six specific methods that companies have used successfully to reduce their inventory. One common attribute of these successes is that they also build teamwork among the people. Every business operation today is concerned with methods to improve customer service. The real trick is to accomplish that task without increasing inventory. We are all concerned with improving our skills at keeping inventory low.

ANALYSIS MODEL FOR INVENTORY MANAGEMENT

Directory of Open Access Journals (Sweden)

CAMELIA BURJA

2010-01-01

Full Text Available The inventory represents an essential component for the assets of the enterprise and the economic analysis gives them special importance because their accurate management determines the achievement of the activity object and the financial results. The efficient management of inventory requires ensuring an optimum level for them, which will guarantee the normal functioning of the activity with minimum inventory expenses and funds which are immobilised. The paper presents an analysis model for inventory management based on their rotation speed and the correlation with the sales volume illustrated in an adequate study. The highlighting of the influence factors on the efficient inventory management ensures the useful information needed to justify managerial decisions, which will lead to a balancedfinancial position and to increased company performance.

National Wetlands Inventory Polygons

Data.gov (United States)

Minnesota Department of Natural Resources — Wetland area features mapped as part of the National Wetlands Inventory (NWI). The National Wetlands Inventory is a national program sponsored by the US Fish and...

10 CFR 39.37 - Physical inventory.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Physical inventory. 39.37 Section 39.37 Energy NUCLEAR... inventory. Each licensee shall conduct a semi-annual physical inventory to account for all licensed material received and possessed under the license. The licensee shall retain records of the inventory for 3 years...

Base-age invariance and inventory projections

Science.gov (United States)

C. J. Cieszewski; R. L. Bailey; B. E. Borders; G. H. Brister; B. D. Shiver

2000-01-01

One of the most important functions of forest inventory is to facilitate management decisions towards forest sustainability based on inventory projections into the future. Therefore, most forest inventories are used for predicting future states of the forests, in modern forestry the most common methods used in inventory projections are based on implicit functions...

SUBDOSA: a computer program for calculating external doses from accidental atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Strenge, D.L.; Watson, E.C.; Houston, J.R.

1975-06-01

A computer program, SUBDOSA, was developed for calculating external γ and β doses to individuals from the accidental release of radionuclides to the atmosphere. Characteristics of SUBDOSA are: doses from both γ and β radiation are calculated as a function of depth in tissue, summed and reported as skin, eye, gonadal, and total body dose; doses are calculated for releases within each of several release time intervals and nuclide inventories and atmospheric dispersion conditions are considered for each time interval; radioactive decay is considered during the release and/or transit using a chain decay scheme with branching to account for transitions to and from isomeric states; the dose from gamma radiation is calculated using a numerical integration technique to account for the finite size of the plume; and the program computes and lists the normalized air concentrations at ground level as a function of distance from the point of release. (auth)

Historical releases of radioactivity to the environment from ORNL

International Nuclear Information System (INIS)

Ohnesorge, W.F.

1986-05-01

This report gives a brief history and assessment of ORNL radionuclide releases to the environment. A short history and an inventory of radioactivity disposed of by shallow land burial and hydrofracture techniques are given along with a brief discussion of the potential environmental impact of these disposed materials. The data available for this report varied greatly in quality. Data on contaminated liquid waste and liquids discharged to the environment are much more reliable than early data on contaminated air discharges and contaminated solid waste. Data for more recent years are more complete and reliable than data obtained from records dating back to the early history of the laboratory. The data presented here do not include materials retrievably stored (with the exception of uranium solid waste data) or inventories of materials stored in operating or surplus facilities since these materials presently have no contact with or loss to the environment

Fast Bayesian Non-Negative Matrix Factorisation and Tri-Factorisation

DEFF Research Database (Denmark)

Brouwer, Thomas; Frellsen, Jes; Liò, Pietro

We present a fast variational Bayesian algorithm for performing non-negative matrix factorisation and tri-factorisation. We show that our approach achieves faster convergence per iteration and timestep (wall-clock) than Gibbs sampling and non-probabilistic approaches, and do not require additional...... samples to estimate the posterior. We show that in particular for matrix tri-factorisation convergence is difficult, but our variational Bayesian approach offers a fast solution, allowing the tri-factorisation approach to be used more effectively....

Annual Danish emissions inventory report to UNECE. Inventory 1990 - 2002

Energy Technology Data Exchange (ETDEWEB)

Illerup, J B; Nielsen, M; Winther, M; Hjort Mikkelsen, M; Lyck, E; Hoffmann, L; Fauser, P

2004-05-01

This report is a documentation report on the emission inventories for Denmark as reported to the UNECE Secretariat under the Convention on Long Range Transboundary Air Pollution due by 15 February 2004. The report contains information on Denmark's emission inventories regarding emissions of (1) SOx for the years 1980-2002, (2) NOx, CO, NMVOC and NH{sub 3} for the years 1985-2002; (3) Particulate matter: TSP, PM10, PM2.5 for the years 2000-2002, (4) Heavy Metals: Pb, Cd, Hg, As, Cr, Cu, Ni, Se and Zn for the years 1990-2002, and (5) Polyaromatic hydrocarbons (PAH): Benzo(a)pyrene, benzo(b)fluoranthene, benzo(k)fluoranthene and indeno(1,2,3-cd)pyrene for the years 1990-2002. Furthermore, the report contains information on background data for emissions inventory. (au)

Annual Danish emissions inventory report to UNECE. Inventory 1990 - 2002

Energy Technology Data Exchange (ETDEWEB)

Illerup, J.B.; Nielsen, M.; Winther, M.; Hjort Mikkelsen, M.; Lyck, E.; Hoffmann, L.; Fauser, P.

2004-05-01

This report is a documentation report on the emission inventories for Denmark as reported to the UNECE Secretariat under the Convention on Long Range Transboundary Air Pollution due by 15 February 2004. The report contains information on Denmark's emission inventories regarding emissions of (1) SOx for the years 1980-2002, (2) NOx, CO, NMVOC and NH{sub 3} for the years 1985-2002; (3) Particulate matter: TSP, PM10, PM2.5 for the years 2000-2002, (4) Heavy Metals: Pb, Cd, Hg, As, Cr, Cu, Ni, Se and Zn for the years 1990-2002, and (5) Polyaromatic hydrocarbons (PAH): Benzo(a)pyrene, benzo(b)fluoranthene, benzo(k)fluoranthene and indeno(1,2,3-cd)pyrene for the years 1990-2002. Furthermore, the report contains information on background data for emissions inventory. (au)

Recent evidence on the muted inventory cycle

OpenAIRE

Andrew J. Filardo

1995-01-01

Inventories play an important role in business cycles. Inventory build-ups add momentum to the economy during expansions, while inventory liquidations sap economic strength during recessions. In addition, because inventory fluctuations are notoriously difficult to predict, they present considerable uncertainty in assessing the economic outlook.> The role of inventories in shaping the current outlook for the U.S. economy is particularly uncertain. In the early 1990s, inventory swings appeared ...

Integrated inventory information system

Digital Repository Service at National Institute of Oceanography (India)

Sarupria, J.S.; Kunte, P.D.

The nature of oceanographic data and the management of inventory level information are described in Integrated Inventory Information System (IIIS). It is shown how a ROSCOPO (report on observations/samples collected during oceanographic programme...

30 CFR 220.032 - Inventories.

Science.gov (United States)

2010-07-01

... operations. The accumulation of surplus stocks shall be avoided by proper materiel control, inventory and... physical inventory that has not been credited to NPSL operations under § 220.015(a)(2) shall be credited to... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Inventories. 220.032 Section 220.032 Mineral...

Nanotechnology in the real world: Redeveloping the nanomaterial consumer products inventory

Directory of Open Access Journals (Sweden)

Marina E. Vance

2015-08-01

Full Text Available To document the marketing and distribution of nano-enabled products into the commercial marketplace, the Woodrow Wilson International Center for Scholars and the Project on Emerging Nanotechnologies created the Nanotechnology Consumer Products Inventory (CPI in 2005. The objective of this present work is to redevelop the CPI by leading a research effort to increase the usefulness and reliability of this inventory. We created eight new descriptors for consumer products, including information pertaining to the nanomaterials contained in each product. The project was motivated by the recognition that a diverse group of stakeholders from academia, industry, and state/federal government had become highly dependent on the inventory as an important resource and bellweather of the pervasiveness of nanotechnology in society. We interviewed 68 nanotechnology experts to assess key information needs. Their answers guided inventory modifications by providing a clear conceptual framework best suited for user expectations. The revised inventory was released in October 2013. It currently lists 1814 consumer products from 622 companies in 32 countries. The Health and Fitness category contains the most products (762, or 42% of the total. Silver is the most frequently used nanomaterial (435 products, or 24%; however, 49% of the products (889 included in the CPI do not provide the composition of the nanomaterial used in them. About 29% of the CPI (528 products contain nanomaterials suspended in a variety of liquid media and dermal contact is the most likely exposure scenario from their use. The majority (1288 products, or 71% of the products do not present enough supporting information to corroborate the claim that nanomaterials are used. The modified CPI has enabled crowdsourcing capabilities, which allow users to suggest edits to any entry and permits researchers to upload new findings ranging from human and environmental exposure data to complete life cycle

Science Inventory | US EPA

Science.gov (United States)

The Science Inventory is a searchable database of research products primarily from EPA's Office of Research and Development. Science Inventory records provide descriptions of the product, contact information, and links to available printed material or websites.

An inventory of potential PCDD and PCDF emission sources in the mainland of China

Energy Technology Data Exchange (ETDEWEB)

Jin, Jun; Xiaoyan, Tang [Peking Univ., Beijing (China); Peng, Hao [Central Univ. for Nationalities, Beijing (China)

2004-09-15

Polychlorinated dibenzo-p-dioxin (PCDD) and polychlorinated dibenzofurans (PCDF) are widespread environmental pollutants. A number of countries have developed national inventories of PCDD/F emission, such as USA, EU Nations and Japan. However, due to the lack of PCDD/F data measured in China and the uncertain nature of the documentation available on emission factors, the report on inventories of dioxin emission is absent. With the municipal population growth, economic development and living-standard improvement, China faces many severe environment issues including potential problems related to PCDD/F. The country is aware of potential dioxin sources such as: incineration, iron and steel industry, chemical industry, fires, coal power plant, foundries, PCB in capacitors and transformers, sintering, traffic emission. In 2001, China signed the Stockholm Convention on Persistent Organic Pollutants in Stockholm. Therefore, there is a need for information regarding dioxin emission from these sources for taking actions to reduce and/or eliminate the release of dioxins in China, and reduce human exposure. In this study, we identify those potential PCDD/F emission sources and work out the first inventory on PCDD/F emission into the environment in China.

Comparison and analysis of release scenarios for ground disposal of various nations

International Nuclear Information System (INIS)

Sakata, Sadahiro; Nakai, Kunihiro

1985-01-01

This report is aimed at comparing and analyzing the concept and evaluation methods of varuous foreign countries concerning their release scenarios for ground disposal of low- and high-level radioactive wastes in order to provide helpful information to be used in developing release scenarios for Japan. The groundwater release scenario and human intrusion scenario should particularly be well examined in considering shallow ground disposal of low-level wastes. Assessment of the leaching rate is important for a groundwater release scenario. Experimental data and verification tests are required to support the simplified model to be used for safety assessment. Evaluation of the radioactive nucleide inventory is also important for ground disposal of low-level wastes. An evaluation system should be established as soon as possible. For ground disposal of high-level radioactive wastes, on the other hand, it will become increasingly important to establish performance assessment models for practical evaluation of the rate of release from the engineered barrier and to collect test and verification data for suporting them. (Nogami, K.)

42 CFR 35.41 - Inventory.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Inventory. 35.41 Section 35.41 Public Health PUBLIC... STATION MANAGEMENT Disposal of Money and Effects of Deceased Patients § 35.41 Inventory. Promptly after the death of a patient in a station or hospital of the Service, an inventory of his money and effects...

New mechanism for enhancing ash removal efficiency and reducing tritium inventory

International Nuclear Information System (INIS)

Li Chengyue; Deng Baiquan; Yan Jiancheng

2007-01-01

A new mechanism is suggested to suppress ash particle back streams in the divertor region of our fusion experimental breeder (FEB) reactor for enhancing the ash removal efficiency and reducing the tritium inventory by applications of the nonlinear effect of high power rf ponderomotive force potential which reflects the plate-released and re-ionized He + back to the plate. Meanwhile, the potential does not hinder α particles, which are coming from scraping of the layer, flowing to the target plate. However, it does stop tritium ions flowing to the target. Based on the FEB design parameters, our calculations have shown that the ash removal efficiency can be improved by as much as 40% if the parallel component of rf field 150-200 V/cm is applied to the location at a perpendicular distance L=20 cm apart from the plate and the plate-recycling neutral helium atom energy is about 0.75 eV, at the same time, the tritium inventory can be reduced to some extent. (authors)

Blood inventory management: hospital best practice.

Science.gov (United States)

Stanger, Sebastian H W; Yates, Nicola; Wilding, Richard; Cotton, Sue

2012-04-01

Blood is a perishable product, and hence good management of inventories is crucial. Blood inventory management is a trade-off between shortage and wastage. The challenge is to keep enough stock to ensure a 100% supply of blood while keeping time expiry losses at a minimum. This article focuses on inventory management of red blood cells in hospital transfusion laboratories to derive principles of best practice and makes recommendations that will ensure losses due to time expiry are kept to a minimum. The literature was reviewed to identify available models for perishable inventory management. Historical data from the UK blood supply chain was analyzed to identify hospitals with good inventory management practice and low wastage levels. Transfusion laboratory managers in the selected hospitals were interviewed in 7 case studies with the aim of identifying drivers for low wastage and good inventory management practice. The findings from the case studies were compared with the literature. The extant literature asserts that the drivers for good inventory performance are the use of complex inventory models and algorithms. This study has found this not to be the case. Instead, good performance is driven by the quality of transfusion laboratory staff, who must be skilled, regularly trained, and experienced. Electronic crossmatching, transparency of the inventory, and simple management procedures also facilitate good performance. Copyright © 2012 Elsevier Inc. All rights reserved.

Thermal effect of periodical bakeout on tritium inventory in first wall and permeation to coolant in reactor life

International Nuclear Information System (INIS)

Nakahara, Katsuhiko

1989-01-01

In view of safety, it is very important to control the tritium inventory in first walls and permeation to the coolant. A time-dependent diffusion and temperature calculation code, TPERM, was developed. Using this code, a numerical study on the long term effects of the bakeout temperature on tritium inventory and tritium permeation to the coolant was made. In this study, an FER type first wall (stainless steel) was considered and a cyclic operation (one cycle includes a plasma burn phase and a bakeout phase) was assumed. The results are as follows: (i) There is almost no difference in the tritium inventory in the first wall between the operation with 150 0 C-bakeout and the continuous burning operation (without bakeout). In both cases there is not tritium permeation to the coolant at 5 years' integrated burn time. The 150 0 C-bakeout is effective to release tritium in the surface (to 0.1 mm depth) region on the plasma side, but it is not effective to decrease the tritium inventory over the reactor life. (ii) To decrease the tritium inventory, a bakeout at a temperature higher than 150 0 C is necessary. But a high temperature bakeout causes earlier tritium permeation to the coolant. (iii) From these results it is suggested that the decrease the tritium inventory over the reactor life by bakeout, some form of protection against tritium permeation or a decontamination device in the cooling (or bakeout) system becomes necessary. (orig.)

A contemporary national nitrogen inventory as a benchmark for future progress in mitigating nitrogen pollution in the USA

Science.gov (United States)

Boyer, E. W.; Galloway, J. N.; Theis, T.; Alexander, R. B.

2011-12-01

We present a contemporary inventory of reactive nitrogen (Nr) inputs to land, air, and water in the United States. Inputs of Nr to the nation and the world have been increasing, largely due to human activities associated with food production and energy consumption via the combustion of fossil fuels and biofuels. Despite the obvious essential benefits of a plentiful supply of food and energy, the adverse consequences associated with the accumulation of Nr in the environment are large. Most of the Nr created by anthropogenic activities is released to the environment, often with unintended negative consequences. The greater the inputs of Nr to the landscape, the greater the potential for negative effects, caused by greenhouse gas production, ground level ozone, acid deposition, and Nr overload that can contribute to climate change, degradation of soils and vegetation, acidification of surface waters, coastal eutrophication, hypoxia and habitat loss. Here, we present a consistent accounting method for quantifying Nr sources and transport that was used in our inventory, and discuss associated data needs for tallying Nr inputs at regional scales. The inventory is a necessary tool for exploring the role of Nr contributed to the environment from various sources (e.g., from fertilizers, manure, biological fixation, human waste, atmospheric deposition) and from various industrial sectors (e.g., from agriculture, transportation, electricity generation). Agriculture and use of fertilizers to produce food, feed, and fiber (including bioenergy and biological nitrogen fixation) and combustion of fossil fuels are the largest sources of Nr released into the environment in the USA. Our inventory is currently being used by the U.S. Environmental Protection Agency as a benchmark of the current Nr situation against which future progress can be assessed -- amidst changing Nr inputs and implementation of policy and management strategies to mitigate Nr pollution.

Uniformity: The key to better inventory management

International Nuclear Information System (INIS)

Boshears, G.

1993-01-01

The objective of this paper is to show how uniformity in describing parts and materials can be the key ingredient to more effective inventory management. Although most nuclear utilities have some type of computer system for maintenance management as well as materials tracking, few have a system to provide the various users with complete information about parts and material in stock. One of the industry's most perplexing problems is How do you know, and find, the item you need to repair a particular piece of equipment or component? In many instances it is easier to order a new one from the manufacturer rather than try to find it on-site, which can result in inaccurate usage records, over-stocking, frustration, and strain on cash flow. What is needed is a higher degree of uniformity within a station, and a utility, of catalog descriptions for parts and material that will satisfy all users-planners, craftsmen, warehouse personnel, and buyers. The results of attaining this uniformity are improved performance through searchability, duplicate stock avoidance, interchangeability, substitutability, and more accurate bills of material; economic benefits will also be noted

Upper-bound fission product release assessment for large break LOCA in CANFLEX bundle reactor core

International Nuclear Information System (INIS)

Oh, Duk Ju; Lee, Kang Moon

1996-07-01

Quarter-core gap inventory assessment for CANDU-6 reactor core loaded with CANFLEX fuel bundles has been performed as one of the licensing safety analyses required for 24 natural uranium CANFLEX bundle irradiation in CANDU-6 reactor. The quarter-core gap inventory for the CANFLEX bundle core is 5 - 10 times lower than that for the standard bundle core, depending on the half-life of the isotope. The lower gap inventory of the CANFLEX bundle core is attributed to the lower linear power of the CANFLEX bundle compared with the standard bundle. However, the whole core total inventories for both the CANFLEX and standard bundle cores are nearly the same. The 6 - 8 times lower upper-bound fission product releases of the CANFLEX bundle core for large break LOCA than those of the standard bundle core imply that the loading of 24 natural uranium CANFLEX bundles would improve the predicted consequences of the postulated accident described in the Wolsung 2 safety report. 2 tabs., 6 figs., 3 refs. (Author)

Optimization of inventory management in furniture manufacturing

OpenAIRE

Karkauskas, Justinas

2017-01-01

Aim of research - to present inventory management optimization guidelines for furniture manufacturing company, based on analysis of scientific literature and empirical research. Tasks of the Issue: • Disclose problems of inventory management in furniture manufacturing sector; • To analyze theoretical inventory management decisions; • To develop theoretical inventory management optimization model; • Do empirical research of inventory management and present offers for optimizatio...

Comparison of global inventories of CO_2 emissions from biomass burning during 2002–2011 derived from multiple satellite products

International Nuclear Information System (INIS)

Shi, Yusheng; Matsunaga, Tsuneo; Saito, Makoto; Yamaguchi, Yasushi; Chen, Xuehong

2015-01-01

This study compared five widely used globally gridded biomass burning emissions inventories for the 2002–2011 period (Global Fire Emissions Database 3 (GFED3), Global Fire Emissions Database 4 (GFED4), Global Fire Assimilation System 1.0 (GFAS1.0), Fire INventory from NCAR 1.0 (FINN1.0) and Global Inventory for Chemistry-Climate studies-GFED4 (G-G)). Average annual CO_2 emissions range from 6521.3 to 9661.5 Tg year"−"1 for five inventories, with extensive amounts in Africa, South America and Southeast Asia. Coefficient of Variation for Southern America, Northern and Southern Africa are 30%, 39% and 48%. Globally, the majority of CO_2 emissions are released from savanna burnings, followed by forest and cropland burnings. The largest differences among the five inventories are mainly attributable to the overestimation of CO_2 emissions by FINN1.0 in Southeast Asia savanna and cropland burning, and underestimation in Southern Africa savanna and Amazon forest burning. The overestimation in Africa by G-G also contributes to the differences. - Highlights: • Five widely used global biomass burning emissions inventories were compared. • Global CO_2 emissions compared well while regional differences are large. • The largest differences were found in Southeast Asia and Southern Africa. • Savanna burning emission was the largest contributor to the global emissions. • Variations in savanna burning emission led to the differences among inventories. - Differences of the five biomass burning CO_2 emissions inventories were found in Southeast Asia and Southern Africa due to the variations in savanna burning emissions estimation.

Tri-Space Framework for Understanding MNC Behaviour and Strategies

DEFF Research Database (Denmark)

Rana, Mohammad Bakhtiar

2015-01-01

This paper presents a framework called ‘Tri-Space’ that comprises three overlapping social spaces, indicating three different concepts: institution and business systems, civil society, and transnational communities. Tri-space framework broadens the horizon of understanding of how MNCs behave...

Hanford inventory program user's manual

International Nuclear Information System (INIS)

Hinkelman, K.C.

1994-01-01

Provides users with instructions and information about accessing and operating the Hanford Inventory Program (HIP) system. The Hanford Inventory Program is an integrated control system that provides a single source for the management and control of equipment, parts, and material warehoused by Westinghouse Hanford Company in various site-wide locations. The inventory is comprised of spare parts and equipment, shop stock, special tools, essential materials, and convenience storage items. The HIP replaced the following systems; ACA, ASP, PICS, FSP, WSR, STP, and RBO. In addition, HIP manages the catalog maintenance function for the General Supplies inventory stocked in the 1164 building and managed by WIMS

Optimal ABC inventory classification using interval programming

NARCIS (Netherlands)

Rezaei, J.; Salimi, N.

2015-01-01

Inventory classification is one of the most important activities in inventory management, whereby inventories are classified into three or more classes. Several inventory classifications have been proposed in the literature, almost all of which have two main shortcomings in common. That is, the

An Analysis of the Optimal Multiobjective Inventory Clustering Decision with Small Quantity and Great Variety Inventory by Applying a DPSO

Science.gov (United States)

Li, Meng-Hua

2014-01-01

When an enterprise has thousands of varieties in its inventory, the use of a single management method could not be a feasible approach. A better way to manage this problem would be to categorise inventory items into several clusters according to inventory decisions and to use different management methods for managing different clusters. The present study applies DPSO (dynamic particle swarm optimisation) to a problem of clustering of inventory items. Without the requirement of prior inventory knowledge, inventory items are automatically clustered into near optimal clustering number. The obtained clustering results should satisfy the inventory objective equation, which consists of different objectives such as total cost, backorder rate, demand relevance, and inventory turnover rate. This study integrates the above four objectives into a multiobjective equation, and inputs the actual inventory items of the enterprise into DPSO. In comparison with other clustering methods, the proposed method can consider different objectives and obtain an overall better solution to obtain better convergence results and inventory decisions. PMID:25197713

INCAP - Applying short-term flexibility to control inventories

OpenAIRE

Lödding , Hermann; Lohmann , Steffen

2011-01-01

Abstract Inventory Based Capacity Control (INCAP) is a very simple method that allows inventory levels to be effectively controlled by using short-term capacity flexibility in make-to-stock settings. Moreover, INCAP can be used for finished goods inventories as well as for semi-finished goods inventories. The basic idea is to define upper and lower inventory limits and to adjust capacities if the inventory level reaches either limit. Should the inventory fall below the lower limit,...

MALAYSIAN WEATHER DATA (TRY) FOR ENERGY SIMULATIONS IN BUILDINGS

DEFF Research Database (Denmark)

Reimann, Gregers Peter

2001-01-01

Detailed energy simulations for buildings in Malaysia have become possible after the recent construction of a Malaysian TRY (Test Reference Year) based on 21 years of hourly weather data from Subang Meteorological Station. The climatic parameters contained in the TRY are dry bulb temperature, wet...

Strategic Inventories in Vertical Contracts

OpenAIRE

Krishnan Anand; Ravi Anupindi; Yehuda Bassok

2008-01-01

Classical reasons for carrying inventory include fixed (nonlinear) production or procurement costs, lead times, nonstationary or uncertain supply/demand, and capacity constraints. The last decade has seen active research in supply chain coordination focusing on the role of incentive contracts to achieve first-best levels of inventory. An extensive literature in industrial organization that studies incentives for vertical controls largely ignores the effect of inventories. Does the ability to ...

Inventories and sales uncertainty\\ud

OpenAIRE

Caglayan, M.; Maioli, S.; Mateut, S.

2011-01-01

We investigate the empirical linkages between sales uncertainty and firms´ inventory investment behavior while controlling for firms´ financial strength. Using large panels of manufacturing firms from several European countries we find that higher sales uncertainty leads to larger stocks of inventories. We also identify an indirect effect of sales uncertainty on inventory accumulation through the financial strength of firms. Our results provide evidence that financial strength mitigates the a...

Clinical and histopathological results following TriPollar radiofrequency skin treatments.

Science.gov (United States)

Kaplan, Haim; Gat, Andrea

2009-06-01

Skin laxity, wrinkles and cellulite are common aesthetic problems associated with the aging process. These symptoms are due to the weakening and thinning of dermal connective tissue and the enlargement of hypodermal fat cells. The aim of this study was to evaluate the safety and efficacy of the TriPollar RF technology in reducing fat and collagen regeneration. Twelve healthy patients underwent weekly treatments on different body sites using the TriPollar technology. Treatment areas were photographed and measured and patient satisfaction was monitored. One abdominal patient consented to a series of TriPollar treatments prior to her scheduled abdominoplasty. A controlled histopathology analysis was performed on skin samples taken during the abdominoplasty procedure. Histopathological examination revealed marked differences between treated and non-treated abdominal skin areas. An increase of 49% in dermal thickness, focal thickening of collagen fibers and focal shrinkage of fat cells was shown following TriPollar treatments. Average patient satisfaction indicated clear satisfaction with the clinical results achieved. The TriPollar is a safe and effective non-invasive technology leading to skin tightening and body shaping. Histology results indicate changes at the dermal and fat layers following TriPollar treatments resulting in increased collagen regeneration and stimulated fat metabolism.

77 FR 5280 - Service Contracts Inventory

Science.gov (United States)

2012-02-02

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0023] Service Contracts Inventory AGENCY: Nuclear...) is providing for public information its Inventory of Contracts for Services for Fiscal Year (FY) 2011. The inventory includes service contract actions over $25,000 that were awarded in FY 2011. ADDRESSES...

78 FR 10642 - Service Contracts Inventory

Science.gov (United States)

2013-02-14

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0029] Service Contracts Inventory AGENCY: Nuclear...) is providing for public information its Inventory of Contracts for Services for Fiscal Year (FY) 2012. The inventory includes service contract actions over $25,000 that were awarded in FY 2012. ADDRESSES...

SBA Network Components & Software Inventory

Data.gov (United States)

Small Business Administration — SBA’s Network Components & Software Inventory contains a complete inventory of all devices connected to SBA’s network including workstations, servers, routers,...

48 CFR 49.602-2 - Inventory forms.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Inventory forms. 49.602-2... TERMINATION OF CONTRACTS Contract Termination Forms and Formats 49.602-2 Inventory forms. Standard Form (SF) 1428, Inventory Disposal Schedule, and SF 1429, Inventory Disposal Schedule—Continuation Sheet, shall...

10 CFR 850.20 - Baseline beryllium inventory.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Baseline beryllium inventory. 850.20 Section 850.20 Energy... Baseline beryllium inventory. (a) The responsible employer must develop a baseline inventory of the... inventory, the responsible employer must: (1) Review current and historical records; (2) Interview workers...

An Emission Inventory of Polycyclic Aromatic Hydrocarbons in China

Science.gov (United States)

Mu, Xilong; Zhu, Xianlei; Wang, Xuesong

2015-04-01

Polycyclic Aromatic Hydrocarbons (PAHs) are among the most dangerous compounds due to their high carcinogenic and mutagenic character. Emission inventory provides the primary data to account for the sources of ambient PAHs and server as a necessary database for effective PAHs pollution control. China is experiencing fast economic growth and large energy consumption, which might result in a large amount of PAHs anthropogenic emissions. Therefore, based on the previous studies and combined recently field emission measurements as well as socio-economic activity data, the development of a nationwide PAHs emission inventory is needed. In this work, the emission inventory of 16 PAHs listed as U.S. Environmental Protection Agency priority pollutants in China in the year 2012 is compiled. The emission amounts of PAHs were estimated as annual rates of emission-related activities multiplied by respective emission factors. The activities such as fuel consumption, including fossil fuel and biofuel, and socio-economic statistics were obtained from yearbook released by Chinese central government and/or provincial governments, as well as related industry reports. Emission factors were derived from the related literature. Recently reported emission factors from local measurements were used. The total emissions of PAHs were 120611 ton in 2012. In China, PAHs were emitted predominantly from domestic combustion of coal and biofuel, coking industry and motor vehicles, accounting for 72% of the total amount. PAHs emission profiles were significantly different between China and the other countries. The emission profile in China featured a relatively higher portion of high molecular weight species with carcinogenic potential due to large contributions of domestic combustion and coking industry. Domestic combustion of straw, coal and firewood emitted 19464 ton, 8831 ton, and 5062 ton of PAHs, respectively, which were much higher than those in other countries. Emission per capita showed

SISTEM INVENTORI BARANG DENGAN TEKNOLOGI AJAX

Directory of Open Access Journals (Sweden)

Anna Fitriya

2015-11-01

Full Text Available ABSTRAK Sistem inventori barang pada pertokoan telah banyak dikembangkan untuk meningkatkan efektivitas dan efisiensi. Pada Toko Karya Indah, kegiatan yang berkaitan dengan inventori barang masih dilakukan secara manual sehingga pihak toko kesulitan untuk mengetahui data barang yang masih tersedia, habis, atau hampir habis. Selain itu, proses yang dilakukan membutuhkan waktu yang relatif lama. Oleh karena itu, diperlukan sistem inventori barang. Sistem dibangun dengan bahasa pemrograman PHP dan database MySQL. Sistem disertai teknologi AJAX (Asynchronous JavaScript And XML, khususnya AJAX autocomplete dan AJAX validasi. Hasil yang diperoleh adalah pengolahan data pada sistem inventori barang dengan menggunakan AJAX dapat dilakukan dengan lebih cepat dari pada tanpa AJAX. Kata kunci: sistem inventori, AJAX.

Double shell tanks plutonium inventory assessment

International Nuclear Information System (INIS)

Tusler, L.A.

1995-01-01

This report provides an evaluation that establishes plutonium inventory estimates for all DSTs based on known tank history information, the DST plutonium inventory tracking system, tank characterization measurements, tank transfer records, and estimated average concentration values for the various types of waste. These estimates use data through December 31, 1994, and give plutonium estimates as of January 1, 1995. The plutonium inventory values for the DSTs are given in Section 31. The plutonium inventory estimate is 224 kg for the DSTs and 854 kg for the SSTs for a total of 1078 kg. This value compares favorably with the total plutonium inventory value of 981 kg obtained from the total plutonium production minus plutonium recovery analysis estimates

75 FR 82095 - Service Contracts Inventory

Science.gov (United States)

2010-12-29

... NUCLEAR REGULATORY COMMISSION [NRC-2010-0394] Service Contracts Inventory AGENCY: U.S. Nuclear...) is providing for public information its Inventory of Contracts for Services for Fiscal Year (FY) 2010. The inventory includes service contract actions over $25,000 that were awarded in FY 2010. ADDRESSES...

Student-Life Stress Inventory.

Science.gov (United States)

Gadzella, Bernadette M.; And Others

The reliability of the Student-Life Stress Inventory of B. M. Gadzella (1991) was studied. The inventory consists of 51 items listed in 9 sections indicating different types of stressors (frustrations, conflicts, pressures, changes, and self-imposed stressors) and reactions to the stressors (physiological, emotional, behavioral, and cognitive) as…

Uncertainties in emission inventories

NARCIS (Netherlands)

Aardenne, van J.A.

2002-01-01

Emission inventories provide information about the amount of a pollutant that is emitted to the atmosphere as a result of a specific anthropogenic or natural process at a given time or place. Emission inventories can be used for either policy or scientific purposes. For