The San Vicente reservoir north of San Diego currently has a residence time for

ID: 195 • Letter: T

Question

The San Vicente reservoir north of San Diego currently has a residence time for water of approximately 14 days. The present volume of the reservoir is 111,000,000 m3, but the San Diego County Water Authority hopes to increase the volume of the reservoir to 298,502,604 m3 by the year 2017 in order to have a larger emergency reserve of water.

A. Assuming that minimal water is lost due to evaporation and the total volume remains constant, what is the current rate at which water enters and leaves the San Vicente reservoir?

B. The Environmental Protection Agency (EPA) limit for nitrates in potable water is 45.0 mg/L. If tomorrow, pollution sources upstream of the reservoir were to create an input concentration of NO3 equal to 61.6 mg/L, how long would it take for the water to no longer be considered potable? You may assume that the reservoir initially had only 3.0 mg/L of nitrates and that the reservoir volume is constant.

C. Find an equation for nitrate concentration as a function of time and graph. Make sure to label the initial concentration, the EPA nitrate limits, the steady-state concentration, your answer to B, and the residence time. If the current rate at which water enters and leaves remains the same in 2017, what will the new residence time of water in the reservoir be? Given the new residence time, re-compute your answer to (B).

Explanation / Answer

B)-ANS-

The maximum annual dose resulting from residual radioactive contamination

International Nuclear Information System (INIS)

Pacific Northwest Laboratory has proposed a method for determining acceptable reidual radioactive contamination levels for the unrestricted public use of decommissioned nuclar facilities. This method compares the calculated maximum annual dose received by a maximum-exposed individual with established annual dose limits. While there is currently no guidance on annual dose limits specifically written for post-decommissioning situations, we feel that such guidance consistent with other existing standards is necessary. An example of the method is presented in this paper based on an assumed dose limit of one millirem. Using existing radiation exposure pathway models and data bases describing the chemical and physical properties of radionculides, we have computed annual doses over fifty years of continuous exposure for an example radionuclide inventory for select organs of reference. Annual dose versus time curves are first presented to illustrate the behavior of specific radionuclides. Next, we show annual dose versus time curves for the example radionuclide inventory to illustrate the composite behavior of a mixture. Finally, the calculated acceptable residual surface contamination of the example inventory corresponding to the assumed dose limit of one millirem is presented. 17 refs., 5 figs., 1 tab.

1979-01-01

Maximum permissible dietary contamination after the accidental release of radioactive materials from a nuclear reactor

International Nuclear Information System (INIS)

After the accident to No. 1 pile at Windscale on October 10, 1957 (Atomic Energy Office, 1957), the Atomic Energy Authority asked the Medical Research Council for advice on the maximum intake of certain radioactive isotopes that should be regarded as permissible, under emergency conditions, for members of the general population living in, or deriving food from, an area contaminated owing to an accident to a reactor. The Council's Committee on Protection against Ionizing Radiations, together with its Subcommittees on Internal and External Radiations, has considered this problem, and concludes that the intake of radioactive materials by ingestion of contaminated food would generally be the limiting source of hazard after any such accident. Intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances. In the following report, therefore, the Committee proposes maximum permissible levels of dietary contamination for the relevant isotopes in the emergency conditions envisaged. In proposing these levels, the Protection Committee has used the fullest information available on the radiation doses that would be delivered to different body tissues and at different ages by the isotopes concerned, and on the ways in which these materials would enter the body

1960-01-01

Poster 23. Maximum allowable chloride levels on stainless steel components at the Sizewell 'B' PWR

International Nuclear Information System (INIS)

Work has been undertaken to assess under what environmental conditions and chloride contamination levels corrosion (stress corrosion cracking, intergranular attack and pitting) could occur at the Sizewell 'B' PWR. Based on the results maximum allowable chloride levels have been specified for plant operation and storage. (author).

1992-01-01

Maximum Photovoltaic Penetration Levels on Typical Distribution Feeders: Preprint

Energy Technology Data Exchange (ETDEWEB)

This paper presents simulation results for a taxonomy of typical distribution feeders with various levels of photovoltaic (PV) penetration. For each of the 16 feeders simulated, the maximum PV penetration that did not result in steady-state voltage or current violation is presented for several PV location scenarios: clustered near the feeder source, clustered near the midpoint of the feeder, clustered near the end of the feeder, randomly located, and evenly distributed. In addition, the maximum level of PV is presented for single, large PV systems at each location. Maximum PV penetration was determined by requiring that feeder voltages stay within ANSI Range A and that feeder currents stay within the ranges determined by overcurrent protection devices. Simulations were run in GridLAB-D using hourly time steps over a year with randomized load profiles based on utility data and typical meteorological year weather data. For 86% of the cases simulated, maximum PV penetration was at least 30% of peak load.

Hoke, A.; Butler, R.; Hambrick, J.; Kroposki, B.

2012-07-01

Approach to forecasting daily maximum ozone levels in St. Louis

Science.gov (United States)

Measurements taken in 1976 from the St. Louis Regional Air Pollution Study (RAPS) data base, conducted by EPA, were analyzed to determine an optimum set of air-quality and meteorological variables for predicting maximum ozone levels for each day in 1976. A 'leaps and bounds' regression analysis was used to identify the best subset of variables. Three particular variables, the 9 a.m. ozone level, the forecasted maximum temperature, and the 6-9 a.m. averaged wind speed, have useful forecasting utility. The trajectory history of air masses entering St. Louis was studied, and it was concluded that transport-related variables contribute to the appearance of very high ozone levels. The final empirical forecast model predicts the daily maximum ozone over 341 days with a standard deviation of 11 ppb, which approaches the estimated error.

Prior, E. J.; Schiess, J. R.; Mcdougal, D. S.

1981-01-01

Abnormal ''Contamination' Levels On Garden Appliances

International Nuclear Information System (INIS)

During routine contamination checks we encountered an abnormal high level of Alpha and Beta emitting radioisotopes on working gloves of employees of the gardening department. It came out that the source was due to ''contamination'' levels on steering wheels of some gardening machines. In order to ensure that no real contamination of these workers was involved , a series of checks was started to identity the source of the abnormal levels found during monitoring.

1999-12-20

Maximum surface level and temperature histories for Hanford waste tanks

International Nuclear Information System (INIS)

Radioactive defense waste resulting from the chemical processing of spent nuclear fuel has been accumulating at the Hanford Site since 1944. This waste is stored in underground waste-storage tanks. The Hanford Site Tank Farm Facilities Interim Safety Basis (ISB) provides a ready reference to the safety envelope for applicable tank farm facilities and installations. During preparation of the ISB, tank structural integrity concerns were identified as a key element in defining the safety envelope. These concerns, along with several deficiencies in the technical bases associated with the structural integrity issues and the corresponding operational limits/controls specified for conduct of normal tank farm operations are documented in the ISB. Consequently, a plan was initiated to upgrade the safety envelope technical bases by conducting Accelerated Safety Analyses-Phase 1 (ASA-Phase 1) sensitivity studies and additional structural evaluations. The purpose of this report is to facilitate the ASA-Phase 1 studies and future analyses of the single-shell tanks (SSTs) and double-shell tanks (DSTs) by compiling a quantitative summary of some of the past operating conditions the tanks have experienced during their existence. This report documents the available summaries of recorded maximum surface levels and maximum waste temperatures and references other sources for more specific data.

1994-01-01

Maximum surface level and temperature histories for Hanford waste tanks

Energy Technology Data Exchange (ETDEWEB)

Flanagan, B.D.; Ha, N.D.; Huisingh, J.S.

1994-09-02

Maximum allowable power levels in HANARO fuel channels

International Nuclear Information System (INIS)

HANARO is a light-water-cooled and heavy-water-reflected research reactor designed and operated at a full power of 30 MWth. The compact core is composed of 23 hexagonal and 16 circular flow channels. Each hexagonal flow channel, formed by a hexagonal flow tube, is loaded with a hexagonal fuel bundle which has 36 fuel elements. The circular flow channel formed by a circular flow tube is loaded with a circular fuel bundle which has 18 fuel elements. In the thermalhydraulic design of the HANARO, the design limit values for the three design parameters were determined using the statistical thermal design method. The design basis is that for the normal operation and the operational occurrences, the physical phenomena like as CHF (Critical Heat Flux) or ONB(Onset of Nucleate Boiling) would not occur with the 95% of probability and the 95% confidence level as illustrated in Figure 1. In this paper, the maximum power levels satisfying the design limits were obtained and the safe operational ranges were made for the four different fuel channels

2005-01-01

Maximum entropy estimation of a Benzene contaminated plume using ecotoxicological assays

British Library Electronic Table of Contents (United Kingdom)

Ecotoxicological bioassays, e.g. based on Danio rerio teratogenicity (DarT) or the acute luminescence inhibition with Vibrio fischeri, could potentially lead to significant benefits for detecting on site contaminations on qualitative or semi-quantitative bases. The aim was to use the observed effects of two ecotoxicological assays for estimating the extent of a Benzene groundwater contamination plume. We used a Maximum Entropy (MaxEnt) method to rebuild a bivariate probability table that links the observed toxicity from the bioassays with Benzene concentrations. Compared with direct mapping of the contamination plume as obtained from groundwater samples, the MaxEnt concentration map exhibits on average slightly higher concentrations though the global pattern is close to it. This suggest Ma...

Wahyudi, A.; Bartzke, M.; Kuster, E.; Bogaert, P.

2013-01-01

Maximum entropy estimation of a Benzene contaminated plume using ecotoxicological assays.

UK PubMed Central (United Kingdom)

Wahyudi A; Bartzke M; K

Navigate

The San Francisco power company faces a total cost function of TC= (1/2)Q 2 + 10

The San Vicente reservoir north of San Diego currently has a residence time for

Integrity-first tutoring: explanations and feedback only — we do not complete graded work. Learn more.

The San Vicente reservoir north of San Diego currently has a residence time for

Question

Explanation / Answer

Related Questions

Navigate