Facility effluent monitoring plan for the plutonium uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Facility effluent monitoring plan for the plutonium uranium extraction facility

International Nuclear Information System (INIS)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

International Nuclear Information System (INIS)

Greager, E.M.

1997-01-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years

Facility effluent monitoring plan for the plutonium-uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, NM (United States)

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Legal provisions governing gaseous effluents radiological monitoring

International Nuclear Information System (INIS)

Winkelmann, I.

1985-01-01

This contribution explains the main provisions governing radiological monitoring of gaseous effluents from LWR type nuclear power plants. KTA rule 1503.1 defines the measuring methods and tasks to be fulfilled by reactor operators in order to safeguard due monitoring and accounting of radioactive substances in the plants' gaseous effluents. The routine measurements are checked by a supervisory programme by an independent expert. The routine controls include analysis of filter samples, comparative measurement of radioactive noble gases, interlaboratory comparisons, and comparative evaluation of measured values. (DG) [de

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontage, S.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

Facility Effluent Monitoring Plan for the Plutonium Finishing Plant (PFP); FINAL

International Nuclear Information System (INIS)

FRAZIER, T.P.

1999-01-01

A facility effluent monitoring plan is required by the U. S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. To ensure the long-range integrity of the effluent monitoring systems, an update to this facility effluent monitoring plan is required whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document is reviewed annually even if there are no operational changes, and is updated, at a minimum, every 3 years

Facility Effluent Monitoring Plan for the 222-S Laboratory

International Nuclear Information System (INIS)

Robinson, A.V.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems against applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. The current operation of the 222-S facilities includes the provision of analytical and radiological chemistry services in support of Hanford Site processing plants. The emphasis is on waste management, chemical processing, environmental monitoring effluent programs at B Plant, the Uranium Oxide Plant, Tank Farms, the 242-A Evaporator, the Waste Encapsulation and Storage Facility, the Plutonium-Uranium Extraction Facility, the Plutonium Finishing Plant, process development/impact activities, and essential materials. The laboratory also supplies analytical services in support of ongoing waste tank characterization

Facility effluent monitoring plan for the 324 Facility

International Nuclear Information System (INIS)

1994-11-01

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

High sensitivity on-line monitor for radioactive effluent

Energy Technology Data Exchange (ETDEWEB)

Sasaki, Toshimi [Tohoku Electric Power Co. Ltd., Sendai (Japan); Ishizuka, Akira; Abe, Eisuke; Inoue, Yasuhiko; Fujii, Masaaki; Kitaguchi, Hiroshi; Doi, Akira

1983-04-01

A new approach for a highly sensitive effluent monitor is presented. The free flow type monitor, which consists of a straightener, nozzle, monitoring section and ..gamma..-ray detector, is demonstrated to be effective in providing long term stability. The 160 start-and-stop cycles of effluent discharge were repeated in a 120-h testing period. Results showed a background increase was not observed for the free flow type monitor. The background count rate was calibrated to the lowest detection limit to be 2.2 x 10/sup -2/ Bq/ml for a 300 s measurement time.

Atomics International environmental monitoring and facility effluent annual report, 1976

International Nuclear Information System (INIS)

Moore, J.D.

1977-01-01

Environmental and facility effluent radioactivity monitoring at Atomics International (AI) is performend by the Radiation and Nuclear Safety Unit of the Health, Safety, and Radiation Services Department. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from AI sites. Continuous ambient air sampling and thermoluminescent dosimetry are performed on site for monitoring airborne radioactivity and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from AI facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituents in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1976. The results of a special soil plutonium survey performed during the year are also summarized

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

International Nuclear Information System (INIS)

Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

2009-01-01

The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

General principles governing sampling and measurement techniques for monitoring radioactive effluents from nuclear facilities

International Nuclear Information System (INIS)

Fitoussi, L.

1978-01-01

An explanation is given of the need to monitor the release of radioactive gases and liquid effluents from nuclear facilities, with particular emphasis on the ICRP recommendations and on the interest in this problem shown by the larger international organizations. This is followed by a description of the classes of radionuclides that are normally monitored in this way. The characteristics of monitoring 'in line' and 'by sample taking' are described; the disadvantages of in line monitoring and the problem of sample representativity are discussed. There follows an account of the general principles for measuring gaseous and liquid effluents that are applied in the techniques normally employed at nuclear facilities. Standards relating to the specifications for monitoring instruments are at present being devised by the International Electrotechnical Commission, and there are still major differences in national practices, at least as far as measurement thresholds are concerned. In conclusion, it is shown that harmonization of practices and standardization of equipment would probably help to make international relations in the field more productive. (author)

Facility effluent monitoring plan for the tank farm facility

Energy Technology Data Exchange (ETDEWEB)

Crummel, G.M.

1998-05-18

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

Energy Technology Data Exchange (ETDEWEB)

DAVIS, W.E.

2000-03-08

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

DAVIS, W.E.

2000-01-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years

Facility effluent monitoring plan for the fast flux test facility

International Nuclear Information System (INIS)

Nickels, J.M.; Dahl, N.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A Facility Effluent Monitoring Plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Summarization of radioactive effluent monitoring in Daya Bay Nuclear Power Station 1994-2002

International Nuclear Information System (INIS)

Ouyang Junjie; Chen Yue

2004-01-01

This paper introduces the radioactive effluent monitoring systems, measurement and quality control methods used in Daya Bay Nuclear Power Station from its commercial operation in 1994. The main work and experiences for the management of effluent release are discussed and analyzed. The radwaste data appear declining trend and are far blow the annual limit approved by the national Environmental Protection Bureau since 1995. The normalized release (unit GBq/GWa) of 9 years is as follows: liquid nuclides (except tritium) 11.1, liquid tritium 1.91 x 10 4 , noble gas 2.03 x 10 4 , halogen 0.13, aerosol 7.57 x 10 -3 . For 110m Ag, the average release from 1998 to 2002 has been reduced to 1/7 of the quantity in 1997

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Nickels, J.M.; Geiger, J.L.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified. in. A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Effluent Treatment Facility tritium emissions monitoring

International Nuclear Information System (INIS)

Dunn, D.L.

1991-01-01

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

Management of radioactive effluents from research Reactors and PHWRs

International Nuclear Information System (INIS)

Bodke, S.B.; Surender Kumar; Sinha, P.K.; Budhwar, R.K.; Raj, Kanwar

2006-01-01

Indian nuclear power programme is mainly based on pressurized heavy water reactors (PHWRs). In addition we have research reactors namely Apsara, CIRUS, Dhruva at Trombay. The operation and maintenance activities of these reactors generate radioactive liquid waste. These wastes require effective management so that the release of radioactivity to the environment is well within the authorized limits. India is self reliant in the design, erection, commissioning and operation of effluent management system for nuclear reactors. Segregation at source based on nature of effluents and radioactivity content is the first and foremost step in the over all management of liquid effluents. The effluents from the power reactors contain mainly activation products like 3 H. It also contains fission products like 137 Cs. Containment of these radionuclide along with 60 Co, 90 Sr, 131 I plays an important part in liquid waste management. Treatment processes for decontamination of these radionuclide include chemical treatment, ion exchange, evaporation etc. Effluents after treatment are monitored and discharged to the nearby water body after filtration and dilution. The concentrates from the processes are conditioned in cement matrix and disposed in Near Surface Disposal Facilities (NSDFs) co-located at each site. Some times large quantity of effluents with higher radioactivity concentration may get generated from the abnormal operation such as failure of heat exchangers. These effluents are handled on a campaign basis for which adequate storage capacity is provided. The treatment is given taking into consideration the required decontamination factor (DF), capacities of available treatment process, discharge limits and the availability of the dilution water. Similarly large quantities of effluents may get generated during fuel clad failure incident in reactors. In such situation, as in CIRUS large volume of effluent containing higher radioactivity are generated and are managed by delay

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

1994-11-01

The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Improved technique for in situ measurement of radioactivity in liquid effluents

International Nuclear Information System (INIS)

Balasundar, S.; Jose, M.T.; Ravi, T.; Sundaram, V.M.; Raghunath, V.M.

1993-01-01

As a pre-requisite for handling and disposal of radioactive liquid effluents, they should be categorized according to their chemical nature and the type and level of radioactivity. A continuous monitoring of these effluents is necessary to assess the discharged activity and to detect any unusually large increase in the activity level. It may also be required to assess the beta, gamma specific activities in the effluents independently instead of just combined beta-gamma activity as is generally done. (author). 1 ref., 2 tabs

Facility Effluent Monitoring Plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Carter, G.J.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updates as a minimum every three years

Facility effluent monitoring plan for K area spent fuel storage basin

International Nuclear Information System (INIS)

Hunacek, G.S.

1996-01-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400. 1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in WHC-EP-0438-1, A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the second revision to the original annual report. Long-range integrity of the effluent monitoring system shall be ensured with updates of this report whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1

International Nuclear Information System (INIS)

Lewis, C.J.

1995-10-01

A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

International Nuclear Information System (INIS)

Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

2008-01-01

A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0 8 Bq, 5.7x10 8 Bq and 2.7xl0 8 Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent

Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

International Nuclear Information System (INIS)

Herman, D.R.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

Facility effluent monitoring plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Nickels, J.M.; Lavey, G.H.

1992-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Facility effluent monitoring plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontag, S.

1991-11-01

A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

Facility effluent monitoring plan for the 284-E and 284-W power plants

International Nuclear Information System (INIS)

Nickels, J.M.; Herman, D.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Gaseous radioactive effluent restrictions, measurement, and minimization at a PET/cyclotron facility

International Nuclear Information System (INIS)

Plascjak, P.S.; Kim, K.K.; Googins, S.W.; Meyer, W.C. Jr.

1993-01-01

In the US, restrictions on the release of radioactive effluents from PET (positron emission tomography)/cyclotron facilities are typically imposed by State regulatory agencies and may be based on various methodologies and limits published by numerous agencies. This work presents suitable effluent concentration limits for various chemical forms of radioisotopes routinely produced in PET/cyclotron facilities. They were determined by application of metabolic models defined by ICRP 53 and ICRP 26/30 which will result in compliance with effective dose equivalent limits of 100 mrem per year at the release point. The NIH Cyclotron Facility effluent air monitoring system, environmental dosimetry program, and simple, effective systems for radioactive effluent minimization are also described. (orig.)

Treating radioactive effluent

International Nuclear Information System (INIS)

Kirkham, I.A.

1981-01-01

In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

Facility effluent monitoring plan for the tank farms facilities

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

International Nuclear Information System (INIS)

Shields, K.D.; Ballinger, M.Y.

1999-03-01

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

A guide for preparing Hanford Site facility effluent monitoring plans

International Nuclear Information System (INIS)

Nickels, J.M.

1992-06-01

This document provides guidance on the format and content of effluent monitoring plans for facilities at the Hanford Site. The guidance provided in this document is designed to ensure compliance with US Department of Energy (DOE) Orders 5400.1 (DOE 1988a), 5400.3 (DOE 1989a), 5400.4 (DOE 1989b), 5400.5 (DOE 1990a), 5480.1 (DOE 1982), 5480.11 (DOE 1988b), and 5484.1 (DOE 1981). These require environmental monitoring plans for each site, facility, or process that uses, generates, releases, or manages significant pollutants of radioactive or hazardous materials. In support of DOE Orders 5400.5 (Radiation Protection of the Public and the Environment) and 5400.1 (General Environmental Protection Program), the DOE Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE 1991) should be used to establish elements of a radiological effluent monitoring program in the Facility Effluent Monitoring Plan. Evaluation of facilities for compliance with the US Environmental Protection Agency Clean Air Act of 1977 requirements also is included in the airborne emissions section of the Facility Effluent Monitoring Plans. Sampling Analysis Plans for Liquid Effluents, as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), also are included in the Facility Effluent Monitoring Plans. The Facility Effluent Monitoring Plans shall include complete documentation of gaseous and liquid effluent sampling and monitoring systems

Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

International Nuclear Information System (INIS)

HUNACEK, G.S.

2000-01-01

A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary

Facility effluent monitoring plan for the 325 Facility

International Nuclear Information System (INIS)

1998-01-01

The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Facility Effluent Monitoring Plan for the 3720 Building

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

Facility effluent monitoring

Energy Technology Data Exchange (ETDEWEB)

Gleckler, B.P.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

Reduction of releases of radioactive effluents from light-water-power-reactors in Japan

International Nuclear Information System (INIS)

Yoshida, Y.; Itakura, T.; Kanai, T.

1977-01-01

Japan Atomic Energy Commission established the dose objectives to the population around the light-water-reactors in May, 1975, based on the ''ALAP'' concept. These values are respectively, 5 mrems per year for total body and 15 mrems per year for thyroid of an individual in the critical group in the environs, due to both gaseous and liquid effluents from LWRs in one site. The present paper describes the implications of the dose objective values, control measures which have been adopted to reduce releases of radioactive materials and related technical developments in Japan. The main control measures for reduction of radioactive gaseous effluents are an installation of a charcoal gas holdup system for decay of noble gases and a supply of clean steam for the gland seal of a turbine in BWR, and a storage tank system allowing decay of noble gases in PWR. For liquid effluents are taken measures to re-use them as the primary coolant. Consequently, the amounts of radioactivity released to the environment from any LWR during normal operation have been maintained under the level to meet the above dose objective values. For research reactors, reduction of release of effluents has also been carried out in a similar way to LWRs. In order to establish the techniques applicable for further reduction, studies are being made on the control measures to reduce leakage of radioiodine, an apparatus for removal of krypton, the treatment of laundry waste and measures to remove the crud in the primary coolant. Presentation is also made on the energy-integrated gas monitor for gaseous effluent and systems of measuring γ dose from radioactive cloud descriminating from natural background, which have been developed for effective monitoring thus reduced environmental dose

Nuclear plant refurbishment calls for patience. [Construction of radioactive effluent plant

Energy Technology Data Exchange (ETDEWEB)

Henly, Anna

1989-08-01

All nuclear power plants produce a small quantity of liquid effluent from wash hand basins, showers and surface drains on the site. The effluent is termed low-level radioactive waste and under the 'Radioactive Substances Act' can be discharged into estuaries or the sea. Before a controlled discharge can be made the effluent has to be chemically treated and have any radioactive particulate matter removed. The replacing of the radioactive effluent plant at the Berkeley nuclear power station in the United Kingdom is described, with particular reference to the vigorous safety standards and quality assurance programme operated by the Central Electricity Generating Board. (author).

Effective equivalent dose in the critical group due to release of radioactive effluents

International Nuclear Information System (INIS)

Santos, John W.A. dos; Varandas, Luciana R.; Souza, Denise N.; Souza, Cristiano B.F.; Lima, Sandro Leonardo N.; Mattos, Marcos Fernando M.; Moraes, Jose Adenildo T.

2005-01-01

To ensure that the emissions of radioactive material by liquid and gaseous pathways are below applicable limits it is necessary to evaluate the effective equivalent dose in the critical group, which is a magnitude that takes into consideration the modeling used and the terms radioactive activity source. The calculation of this dose considers each radionuclide released by the activity of Nuclear plant, liquid and gaseous by, and the sum of the values obtained is controlled so that this dose does not exceed the goals of the regulatory body, the CNEN and the goals established by the Nuclear power plant. To hit these targets various controls are used such as: controls for effluent monitors instrumentation, environmental monitoring programs, effluent release controls and dose calculation in the environment. According to the findings, it is concluded that during the period of operation of the plants, this dose is below of the required limits

Hybrid monitoring of environmental radioactivity as a perspective approach to rapid control and prediction of environmental contamination due to NPP wastes and effluents

International Nuclear Information System (INIS)

Eremeev, I.S.; Eremenko, V.A.; Zhernov, V.S.; Makarov, Yu.A.; Matveev, V.V.; Ryzhov, N.V.; Ryazanov, V.V.; Skatkin, V.M.

1985-01-01

Conseptucal model of the system of hybride monitoring of environmental radioactivity due to NPP wastes and effluents is proposed. The model a combination of measuring and simulating monitoring, provides correlation of methods and aims of simulation of environmental contamination spread methods and means of monitoring of its factual distribution in space, methods of separation of technogeneous signals from natural radiation background and provision of the given degree of reliability of results of information processing, in particular periodic coorection, model adaptation according to the factual measurement data

Treatment of radioactive effluents at the Boris Kidric Institute

International Nuclear Information System (INIS)

Bojovic, P.; Drobnik, S.; Popara, D.

1964-10-01

The paper describes the origin, composition and activity of radioactive effluents at the Boris Kidric Institute, their collection at the places or origin, transport to the place of disposal and treatment of some smaller quantities. Special attention has been paid to effluents with short-lived isotopes produced in the Laboratory for radioactive isotope production (author)

Progress in the domain of emissions tracking and environment radioactivity monitoring - Proceedings of the technical days organised by the SFRP Environment Section

International Nuclear Information System (INIS)

Calmet, Dominique; Calvez, Marianne; Rivasseau, Corinne Cea; Monfort, Marguerite; Manificat, Guillaume; Pierrard, Olivier; Couvez, Celine; Masson, Olivier; Bruno, Valerie; Renaud, Philippe; Genova, Zhana; Reynal, Nathalie; Le Coz, Eric; Tchilian, Nathalie; Diana, Jean-Jacques; Beguinel, Philippe; Cortes, Pierre; Puydarrieux, Stephane; Brun, Thierry; Devin, Patrick; Clavel, Benoit; Hemidy, Pierre-Yves; Gontier, Gilles; Delloye, Thierry; Mailliat, Alain; Ferreri, Giovanni; LECLERC, Elisabeth

2015-11-01

The Environment Section of the French Society of Radiation Protection (SFRP) organized a technical meeting on the progress made in the domain of emissions tracking and environment radioactivity monitoring. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Environment monitoring at the global, national and local scale: historical overview (Dominique CALMET, CEA); 2 - Evolution of radioactivity monitoring in the environment from 1960 to the present day (Guillaume MANIFICAT, IRSN); 3 - Euratom's legal framework (Zhana GENOVA, CTE); 4 - Main regulatory changes during the last decade (Nathalie REYNAL, ASN); 5 - Progress of standardization works on radioactive effluent emissions control and environment monitoring (Philippe BEGUINEL, BNEN); 6 - From operators' self-monitoring to ASN's inspections: a many components control system (Eric LE COZ, ASN); 7 - Control of effluents and emissions management at CEA Centres (Marianne CALVEZ, CEA); 8 - Liquid and gaseous effluents of ITER experimental facility: description and impacts (Pierre CORTES, IO); 9 - Effluents and emissions management strategy at AREVA NC La Hague facility (Stephane PUYDARRIEUX, AREVA); 10 - Radioactive effluents from nuclear facilities ongoing deconstruction: from dimensioning to real effluents (Benoit CLAVEL, EDF); 11 - Radionuclides decontamination process for liquid effluents using micro-algae at the laboratory scale (Corinne RIVASSEAU, CEA); 12 - Radioactive effluents from nuclear medicine services: management, monitoring and impact measurement methods (Nathalie TCHILIAN, ASN); 13 - Evolution history of effluents management and environment monitoring at the Solvay La Rochelle site (Thierry DELLOYE, SOLVAY); 14 - Different international approaches in effluents management and monitoring: example of French and German gaseous effluents - regulation, analyses, accounting rules (Jean-Jacques DIANA, ASN); 15 - Environment

Monitoring of the release of gaseous and aerosol-bound radioactive materials. Pt. 2

International Nuclear Information System (INIS)

1992-01-01

KTA 1503 contains requirements on technical installations and supplementary organizational measures considered necessary in order to monitor the release of gaseous and aerosol-bound radioactive materials. It consists of part 1: Monitoring of the release of radioactive materials together with stack gas during normal operation; part 2: Monitoring of the release of radioactive materials together with stack gas in the event of incidents; part 3: Monitoring of radioactive materials not released together with stack gas. The concept on which this rule is based is to ensure that in the case of incidents during which the result of effluent monitoring remains meaningful, such monitoring can be reliably performed. (orig./HSCH) [de

Radioactive clearance discharge of effluent from nuclear and radiation facilities

International Nuclear Information System (INIS)

Liu Xinhua; Xu Chunyan

2013-01-01

On the basis of the basic concepts of radiation safety management system exemption, exclusion and clearance, we expound that the general industrial gaseous and liquid effluent discharges are exempted or excluded, gaseous and liquid effluent discharged from nuclear and radiation facilities are clearance, and non-radioactive. The main purpose of this paper is to clarify the concepts, reach a consensus that the gaseous and liquid effluent discharged from nuclear and radiation facilities are non-radioactive and have no hazard to human health and natural environment. (authors)

Monitoring programme. Radioactive substances - report for 1994

International Nuclear Information System (INIS)

1995-09-01

The monitoring of radioactive substances in the vicinity of nuclear sites in the United Kingdom by Her Majesty's Inspectorate of Pollution, acts as an independent check on the operator's returns, on the environmental impact of radioactive waste disposal at authorised sites and on radiation doses to critical groups of the public. In 1994 the programme included the analysis of 160 effluent samples, the analysis of low-level solid radioactive waste destined for the British Nuclear Fuels site at Drigg, and the analysis of a total of 290 environmental samples and direct monitoring at over 150 locations. The materials monitored are those that might result in exposure of the public to radiation by non-food pathways and complements monitoring by the Ministry of Agriculture, Food and Fisheries. Radiation exposures by these pathways which may have been incurred in 1994 are similar to those in previous years and, in all cases, fall substantially below the International Commission on Radiological Protection's recommended principal dose limit of 1mSv per year. (UK)

Technical Orders of 10 August 1976 on the limits and procedures applicable to radioactive effluent discharges from nuclear installations

International Nuclear Information System (INIS)

1976-01-01

Seven technical Orders by the competent Ministers (mainly the Ministers of Health, of Industry and Research, of the Quality of Life) lay down the procedures, conditions and limits applicable to gaseous and liquid radioactive effluent discharges from nuclear installations. These Orders of 10 August were published on 12 September 1976 in the Official French Gazette and were made in implementation of the Decree of 6 November 1974 on gaseous radioactive effluent discharges from nuclear installations and the Decree of 31 December 1974 on liquid radioactive effluent discharges from nuclear installations. Apart from the general rules for setting limits and methods for effluent discharges, they specify the measures for environmental monitoring and for control by the Central Service for Protection against Ionizing Radiations. Certain of them contain the general rules for liquid or gaseous effluent discharges from all nuclear installations, while others lay down the rules proper to light water nuclear power plants. Other types of reactor ie. fast breeders are not yet subject to such regulations. (N.E.A.) [fr

Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

International Nuclear Information System (INIS)

Bobric, E.; Murgoci, S.; Popescu, I.; Ibadula, R.

2001-01-01

Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

The discharge of radioactive effluents from the nuclear power programme into western waters of Great Britain

International Nuclear Information System (INIS)

Allday, C.

1977-01-01

A brief account is presented of the British nuclear power programme and the types of radioactive effluent that arise from the power stations and from the Windscale reprocessing plant. Routes by which these effluents could affect human populations, and radiation dose limits which have been laid down, are discussed. The discharge of permitted amounts of activity into western coastal waters of Great Britain, and the requirements for monitoring the discharges, are described. (U.K.)

Environmental system applied to radioactive liquid effluent release

International Nuclear Information System (INIS)

Nisti, Marcelo Bessa

2009-01-01

The current environmental administration considers the productive activity as an environmental system, defined as a group of processes, interactions, parameters and factors involved in the production. This mastering dissertation evaluated the release of the liquid radioactive effluents at Instituto de Pesquisas Energeticas e Nucleares (IPEN), under a systemic environmental study. The study evaluated the source term at IPEN in the period from 2004 to 2008, making use of gamma-ray and alpha spectrometry, instrumental neutron activation analysis, liquid phase scintillation and atomic absorption spectrometry. The employed methodologies were verified using samples from the Intercomparison National Program - PNI/IRD and Reference Materials. The facilities that contributed the most in these releases were the Radiopharmaceutical Center (CR) and the Research Reactor Center (CRPq) with an average of 11,4% and 87,4%, respectively, relative to the present radioactive activity. The sewer system releases were within the radioactive protection regulations, showing the effectiveness of IPEN's Radioactive Effluents Monitoring Program. The concentration of the stable elements Ag, Cd, Cr, Fe, Mn, Ni, Pb and Zn was determined in the liquid effluent in ali the samples from the storage tanks TR1 and CR in the period from 2004 to 2008 and in some of the samples of other IPEN's facilities in the period from 2004 to 2007. Among the analyzed effluents, two samples were higher than the stable elements discharge standards established in the state of Sao Paulo, one sample was higher than the required value of the element cadmium and the other higher than required value of the element zinco The storage tank TR1 discharge flow was estimated in 10,9 ± 0,9 m3 h -1 . The dilution factor at discharge point E1 was estimated using a radiotracers the isotopes 3 H, 137 CS, 60 Co, 54 Mn and 65 Zn, which are commonly released into IPEN's sewer system. The executed radiotracer study was carried out

The management plan of liquid effluent in Korean advanced light water reactor

International Nuclear Information System (INIS)

Kim, S. H.; Lim, H. S.; Jeong, D. W.; Jeong, D. Y.

2001-01-01

Non-radioactive liquid effluent in Korean Advanced Light Water Reactor is transferred and treated in centralized waste treatment facility after the radioactivity in effluent is checked within power block. The liquid effluent from centralized waste treatment facility will be discharged by way of discharge canal in order to be in the sufficient condition. As a result of investigating the radiation monitoring design in accordance with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring design satisfies the regulatory guideline. In relation to sampling and analyses, most systems satisfy the regulatory guideline except for some effluents from turbine building. And, though sampling and analyses are performed after radioactivity is monitored at each system in turbine building, these exceptions in turbine building effluents are expected to cause no significant problems because radioactivity is monitored by direct or indirect methods prior to release from turbine building. Integrated monitoring on liquid effluent from the centralized waste water treatment facility is not necessary because radiation monitoring, sampling and analyses on each system within power block are performed, and operational effectiveness compared with cost according to adding the radiation monitoring equipment is too low. So, whether the radiation monitoring in this effluent is reflected on design or not is planned to be determined through discussion with regulatory authority

Risk-Based Radioactive Liquid Effluent Monitoring Requirements at the U. S. Department of Energy's Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.

2001-01-01

For Department of Energy (DOE) facilities, clear regulatory guidance exists for structuring radiological air emissions monitoring programs. However, there are no parallel regulations for radiological liquid effluent monitoring programs. In order to bridge this gap and to technically justify liquid effluent monitoring decisions at DOE's Savannah River Site, a graded, risk-basked approach has been established to determine the monitoring and sampling criteria to be applied at each liquid discharge point

Radioactive airborne effluent discharged from Tokai reprocessing plant. 1998-2007

International Nuclear Information System (INIS)

Nakada, Akira; Miyauchi, Toru; Akiyama, Kiyomitsu; Momose, Takumaro; Kozawa, Tomoyasu; Yokota, Tomokazu; Ohtomo, Hiroyuki

2008-10-01

This report provides the data set of atmospheric discharges from Tokai reprocessing plant in Tokai-mura, Japan over the period from 1998 to 2007. Daily and weekly data are shown for 85 Kr that is continuously monitored and for the other nuclides (alpha emitters, beta emitters, 3 H, 14 C, 129 I and 131 I) whose activities are evaluated based on weekly samplings (Weekly sampling is continuous for 1 week). The data contained in this report are expected to apply for studying the behavior of the radioactive airborne effluent in the environment. (author)

Radioactive substances monitoring programme. Report for 1995

International Nuclear Information System (INIS)

1995-01-01

The Radioactive Substances Act 1993 provides for controls to be exercised over the use and keeping of radioactive materials and the accumulation and disposal of radioactive wastes. The Environment Agency (the Agency) has been responsible for administration and enforcement of the Act in England and Wales since its formation on 1 April 1996. Prior to this date the work was undertaken by Her Majesty's Inspectorate of Pollution (HMIP). In support of its regulatory functions HMIP commissioned independent monitoring. This report presents the results from monitoring undertaken in 1995. The 1995 HMIP programme required operators of certain sites to provide samples of their liquid effluents for independent radiochemical analysis. The results provide checks on site operators' returns and insights into their quality assurance (QA) procedures and analytical techniques. The analyses were undertaken by the Laboratory of the Government Chemist (LGC) at its laboratories in Teddington, Middlesex. The programme also included checks on solid low level radioactive waste destined for land disposal at the site operated by British Nuclear Fuels plc (BNFL) at Drigg in Cumbria. (author)

Effluent monitoring: Its purpose and value

International Nuclear Information System (INIS)

Schoen, A.A.

1978-01-01

The purpose of effluent monitoring is described in terms of the primary objectives, the most important of which is to verify that the facility is functioning as it was designed and that the waste treatment and effluent control systems are performing as planned and expected. The object of a monitoring programme should be periodically re-examined to ensure that the programme serves a contemporary purpose. The value of the effluent monitoring programme is determined by the extent to which users of the monitoring data, i.e. the operator, the regulating authorities and the public, accept the result as indicating that the plant is operating safely, and in an environmentally acceptable manner. The credibility of the monitoring results is therefore the most important factor determining the value of an effluent monitoring programme. (author)

Studies for improvement of regulatory control on the radioactive effluent released from nuclear facilities

International Nuclear Information System (INIS)

Cheong, Jae Hak; Park, H. M.; Song, M. C.; Lee, K. H.; Jang, J. K.; Chun, J. K.; Jeong, K. H.

2005-05-01

This report contains the second-year results of the research project titled 'Studies for Improvement of Regulatory Control on the Radioactive Effluent Released from Nuclear Facilities' and mainly provides technical and strategic approaches to improve performance of regulatory control on the gaseous effluent released from domestic nuclear facilities. The main result contained here includes overview and technical bases of radioactive gaseous effluent control (Chapter 1), reconsideration of the sensitivity requirements for measurement of radioactivity in gaseous effluent sample (Chapter 2), uncertainty analysis of the calculated radioactivity in gaseous effluent (Chapter 3), and improvement of quantification method of noble gas releases (Chapter 4). In addition, analysis of the impact due to combined sampling of particulate from multiple release points (Chapter 5), comparison of domestic nuclear reactors gaseous effluent data to foreign PWRs (Chapter 6), standardized sampling technique for collection of gaseous tritium (Chapter 7), and application of Xe-133 equivalent concept to gaseous effluent control (Chapter 8) are also provided. As a whole, this report provides a generic approach to improve the performance of regulatory control on the gaseous effluent. Therefore, actual enforcement of the recommendations should be preceded by establishment of a series of action plans reflecting on the site- and facility-specific design and operational features

Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant

International Nuclear Information System (INIS)

Arsov, Lj.

1977-01-01

This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

Radioactive Effluents from Nuclear Power Plants Annual Report 2007

International Nuclear Information System (INIS)

2010-01-01

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

Radioactive Effluents from Nuclear Power Plants Annual Report 2008

International Nuclear Information System (INIS)

2010-01-01

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

Radioactivity monitoring programme of Krsko nuclear power plant

International Nuclear Information System (INIS)

Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

1996-01-01

As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

Energy Technology Data Exchange (ETDEWEB)

Ballinger, Marcel Y.; Gervais, Todd L.

2004-11-15

The Pacific Northwest National Laboratory (PNNL) operates a number of Research & Development (R&D) facilities for the U.S. Department of Energy (DOE) on the Hanford Site. Facility effluent monitoring plans (FEMPs) have been developed to document the facility effluent monitoring portion of the Environmental Monitoring Plan (DOE 2000) for the Hanford Site. Three of PNNL’s R&D facilities, the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling, and individual FEMPs were developed for these facilities in the past. In addition, a balance-of-plant (BOP) FEMP was developed for all other DOE-owned, PNNL-operated facilities at the Hanford Site. Recent changes, including shutdown of buildings and transition of PNNL facilities to the Office of Science, have resulted in retiring the 3720 FEMP and combining the 331 FEMP into the BOP FEMP. This version of the BOP FEMP addresses all DOE-owned, PNNL-operated facilities at the Hanford Site, excepting the Radiochemical Processing Laboratory, which has its own FEMP because of the unique nature of the building and operations. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R&D. R&D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in Appendix A. Potential radioactive airborne emissions in the BOP facilities are estimated annually using a building inventory-based approach provided in federal regulations. Sampling at individual BOP facilities is based on a potential-to-emit assessment. Some of these facilities are considered minor emission points and thus are sampled routinely, but not continuously, to confirm the low emission potential. One facility, the 331 Life Sciences Laboratory, has a major emission point and is sampled continuously. Sampling systems are

Radioactive gases monitor system: tritium, radon, noble gases

International Nuclear Information System (INIS)

Egey, J.Z.; Matatagui, E.

2015-01-01

A system for monitoring the radioactive gases tritium, radon and noble gases is described. We present the description of the sensor and the associated electronics that have been developed to monitor the presence of radioactive gases in air or other gaseous effluents. The system has a high sensitivity and a wide range of operation. The sensor is an ionization chamber, featuring the internal circulation of the gas to monitor and the associated electronics has a resolution better than 10 E-15A (fA). It allows the detection of the individual pulses that are produced during the alpha decay of radon and its daughter elements. The measurement system is made up of a commercial data acquisition system connected to a computer. The acquired data is presented on a graphical display and it is stored for later processing and analysis. We have a system that is of simple construction and versatile. Here we present the experimental results. (authors) [es

Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-06-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs

Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960)

International Nuclear Information System (INIS)

Bovard, P.; Candillon, C.

1960-01-01

Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [fr

Legal provisions governing liquid effluents radiological monitoring

International Nuclear Information System (INIS)

Gans, I.; Ruehle, H.

1985-01-01

The KTA rule 1504 for radiological monitoring of liquid effluents from nuclear installations is explained. As there are no such rules published to date for establishments handling isotopes, some criteria are discussed which in the future ought to form part of a practical guide for liquid effluents monitoring in isotope handling installations. Monitoring measures described refer to liquid effluents from transfer containers, auxiliary cooling equipment, turbine buildings, main cooling installations, and waste air discharges from closed-circuit cooling systems. (DG) [de

Limitation of releases of radioactive effluents for nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Tolksdorf, P.; Buehling, A.

1981-01-01

Empirical values relating to the effluents of nuclear power plants in the Federal Republic of Germany are now available. These values cover a period of several years of operation. The measured emissions of radioactive substances are often very much below the maximum permissible values, based on the dose limits for the environment stipulated in the legal regulations. Extensive technical and administrative measures contribute to the reduction of radioactive effluents. Furthermore, additional possibilities for improvement are mentioned which may lead to a further reduction of radioactive effluents. These are derived from investigations into the release of radioactive substances in nuclear power plants. The licensing procedure in the Federal Republic of Germany in fixing discharge limits is outlined. Proposals are made concerning licence values which may be determined for the radioactive effluents in modern standardized nuclear power plants with light-water reactors. The resulting radiation exposures are quoted for a typical nuclear power plant site. (author)

A risk-based approach to liquid effluent monitoring

Energy Technology Data Exchange (ETDEWEB)

Hull, L.C.

1995-10-01

DOE Order 5400.1 identifies six objectives of a liquid effluent monitoring program. A strategy is proposed that meets these objective in one of two ways: (1) by showing that effluent concentrations are below concentration limits set by permits or are below concentrations that could cause environmental problems or (2) by showing that concentrations in effluent have not changed from a period when treatment processes were in control and there were no unplanned releases. The intensity of liquid effluent monitoring should be graded to the importance of the source being monitored. This can be accomplished by determining the risk posed by the source. A definition of risk is presented that defines risk in terms of the statistical probability of exceeding a release limit and the time available to recover from an exceedance of a release limit. Three examples are presented that show this approach to grading an effluent monitoring program can be implemented at the Idaho National Engineering Laboratory and will reduce monitoring requirements.

A risk-based approach to liquid effluent monitoring

International Nuclear Information System (INIS)

Hull, L.C.

1995-10-01

DOE Order 5400.1 identifies six objectives of a liquid effluent monitoring program. A strategy is proposed that meets these objective in one of two ways: (1) by showing that effluent concentrations are below concentration limits set by permits or are below concentrations that could cause environmental problems or (2) by showing that concentrations in effluent have not changed from a period when treatment processes were in control and there were no unplanned releases. The intensity of liquid effluent monitoring should be graded to the importance of the source being monitored. This can be accomplished by determining the risk posed by the source. A definition of risk is presented that defines risk in terms of the statistical probability of exceeding a release limit and the time available to recover from an exceedance of a release limit. Three examples are presented that show this approach to grading an effluent monitoring program can be implemented at the Idaho National Engineering Laboratory and will reduce monitoring requirements

Processing of miscellaneous radioactive effluents by continous flocculation decantation

International Nuclear Information System (INIS)

Lundy, D.; Matton, P.; Petteau, J.L.; Roofthooft, R.

1985-01-01

In the nuclear power plant of Chooz an installation for flocculation and chemical precipitation has been built to treat miscellaneous radioactive effluents continuously. It is an industrial prototype of 5 m 3 /h resulting of several years of research, first on lab scale in a discontinous system and finally in a continuous pilot plant of small size (500 l/h). The process is based on the adsorption of radioactivity on a floc of copper-ferrocyanide precipitated by ferric chloride. The water is then filtered. After a series of preliminary tests and modifications, it has been possible to develop a technique which satisfies the specified decontamination conditions and to reduce the discharges of radioactivity to the Meuse to only 5 - 10% of the authorized limits. The process aims principally at the treatment of laundry waste, but other effluents such as drains from the rocks, pool water and used decontamination solutions (of the primary pumps) have been treated. A technico-economic evaluation of the process in comparison with evaporation is clearly in favour of the flocculation. 31 figs, 40 tables, 12 refs

USERDA effluent data collection and reporting program

International Nuclear Information System (INIS)

Elle, D.R.; Schoen, A.A.

1978-01-01

Effluent and environmental monitoring has been conducted at United States Energy Research and Development Administration (formerly United States Atomic Energy Commission) facilities and sites virtually since the inception of atomic energy research and development. In 1971, computer systems were developed that permitted storage of information and data characterizing each effluent and onsite discharge point and relevant information on sources, effluent treatment and control systems, and discharge data, and serve as ERDA's computer-based management information systems for compiling waste discharge control and monitoring data on radioactivity released as airborne or liquid effluents or liquid discharges to onsite retention basins at ERDA facilities. The information systems and associated data outputs have proved to be an effective internal management tool for identifying effluent control problem areas and for surveying an agencywide Radioactive Effluent Reduction Program. The trend data facilitate the detection of gradual changes in the effectiveness of waste treatment systems, and errors or oversights in monitoring and data handling. Other computer outputs are useful for identifying effluent release points that have significantly higher or lower concentrations or quantities in the discharge stream than were measured the previous year. The year-to-year trend reports and the extensive computer edit and error checks have improved the reliability of the reported effluent data. Adoption of a uniform, centralized reporting system has improved the understanding and credibility of effluent data, and has allowed management to evaluate the effectiveness of effluent control practices at ERDA facilities. (author)

Limits to radioactive effluents and countermeasures in accidental situations

International Nuclear Information System (INIS)

Nowotny, G.; Gonzalez, A.

1978-01-01

The paper discusses the criteria used by the Argentine Atomic Energy Commission, as competent authority, to set limits to radioactive effluents from nuclear installations. It also discusses the selection of action levels for carrying out countermeasures in accidental situations. (author)

Introduction of a cation in aqueous solution by electrolytic dissolution of metal. Applications to the decontamination of radioactive effluents

International Nuclear Information System (INIS)

Gauchon, Jean-Paul

1979-01-01

This research thesis aims at comparing results obtained in chemical decontamination of radioactive effluents with a metallic cation introduced by metal electro-dissolution or by dose addition. After an overview of methods used for the purification of radioactive effluents and a more precise presentation of chemical co-precipitation, the author reports preliminary tests of the application of chemical co-precipitation to the decontamination of radioactive effluents, reports the analysis of iron, zinc and copper behaviour in aqueous environment by means of thermodynamic diagrams and current-voltage curves. He reports the design and use of two electro-dissolution sets, and the application of copper electrolytic dissolution to the elimination of ruthenium in radioactive effluents. He finally addresses the purification treatment of effluents of nuclear reactors

Statistical evaluation of effluent monitoring data for the 200 Area Treated Effluent Disposal Facility

International Nuclear Information System (INIS)

Chou, C.J.; Johnson, V.G.

2000-01-01

The 200 Area Treated Effluent Disposal Facility (TEDF) consists of a pair of infiltration basins that receive wastewater originating from the 200 West and 200 East Areas of the Hanford Site. TEDF has been in operation since 1995 and is regulated by State Waste Discharge Permit ST 4502 (Ecology 1995) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216. The permit stipulates monitoring requirements for effluent (or end-of-pipe) discharges and groundwater monitoring for TEDF. Groundwater monitoring began in 1992 prior to TEDF construction. Routine effluent monitoring in accordance with the permit requirements began in late April 1995 when the facility began operations. The State Waste Discharge Permit ST 4502 included a special permit condition (S.6). This condition specified a statistical study of the variability of permitted constituents in the effluent from TEDF during its first year of operation. The study was designed to (1) demonstrate compliance with the waste discharge permit; (2) determine the variability of all constituents in the effluent that have enforcement limits, early warning values, and monitoring requirements (WHC 1995); and (3) determine if concentrations of permitted constituents vary with season. Additional and more frequent sampling was conducted for the effluent variability study. Statistical evaluation results were provided in Chou and Johnson (1996). Parts of the original first year sampling and analysis plan (WHC 1995) were continued with routine monitoring required up to the present time

Radioactivity distribution in phosphate products, by-products, effluents, and wastes

International Nuclear Information System (INIS)

Guimond, R.J.; Windham, S.T.

1975-08-01

Phosphate rock throughout the world contains uranium in concentrations ranging from a few ppM to a few hundred ppM. In the United States, phosphate rock normally contains between 100 to 150 ppM uranium. Mining and processing of these ores redistributes much of the uranium daughters among the various products, by-products, and wastes. These materials are then widely dispersed throughout the environment. This redistribution may lead to increased exposure of the public to these naturally-occurring radionuclides. In determining the magnitude of the population exposure caused by this redistribution and in developing environmental standards and controls to prevent contamination of the biosphere from these naturally-occurring radionuclides it is necessary to determine the concentrations and total quantities of these radionuclides in the products, by-products, effluents and wastes of phosphate mining and manufacturing. Samples of phosphate ores, products, by-products, effluents, and wastes were obtained and analyzed for their radioactivity content. Quantities of radioactivity entering the environment through various products, by-products, effluents, and wastes were estimated

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1997

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

1998-01-01

The number of annual sampling and measurements performed in compliance with the operator's monitoring duties have been the same as last year: 364. All measured radioactivity values were at the level of natural environmental radioactivity. Some samples and measurements reflected the fallout from former atmospheric nuclear weapons tests and the accident at the Chernobyl reactor. Personnel dosimetry was performed according to legal requirements of the Radiation Protection Ordinance, as were measurements for the monitoring of ambient doses, dose rates and radioactivity levels in the air of the mine structures. All measured values were below the maximum permissible personal doses and occupational dose limits. Ambient air measurements in the salt mine as in the preceding years detected low amounts of the nuclides H 3, C 14, Pb 210, and the short-lived daughter products of Rn 222 and Rn 220. The calculated radioactivity concentrations in the vicinity of the mine, derived from averaged annual effluents, to some part were below the average natural concentrations of the nuclides. The effluent-induced radiation dose at the most affected location was far below the limits set by the Radiation Protection Ordinance. (orig./CB) [de

Process for processing and conditioning radioactive effluents of low and medium activity

International Nuclear Information System (INIS)

Taponier, Jean; Pierlas, Rene.

1979-01-01

Preferably continuous process for processing radioactive effluents of low and medium activity, comprising an effluent pre-treatment: precipitation of radioactive compounds to form a stable suspension that can be concentrated. Then a mix is made of 0.6 to 2 parts of cement by weight for one part by weight of suspension, from 0.5 to 5% by weight, in relation to the cement, of asbestos fibre and, if necessary, added water for the cement to set, this suspension containing from 15 to 75% by weight of dry extract and a suspension agent. The homogeneous mix achieved is poured into a container [fr

A unique criterion for the classification of the activity of radioactive effluents according to the activity

International Nuclear Information System (INIS)

Tasovac, T.; Bojovic, P.; Svabic, A.

1964-10-01

The present classification of radioactive effluents into categories, i.e. low, medium, high and very high activity, has not been given a definite criterion. Therefore, some categories include specific activities from 2-6 and more potentials. Therefore, it occurs that the category of medium active effluents in one nuclear center is indicated as low active in the second or as highly active in the third. Therefore, a proposal is given in this paper for a unique criterion for the classification of radioactive effluents according to their activities. This proposal is based on the decontamination factors obtained by various methods and the maximum permissible concentrations of radioactive isotopes in water (author)

Radioactivity in the environment. A summary and radiological assessment of the Environment Ageny's monitoring programmes. Report for 1996

International Nuclear Information System (INIS)

1996-01-01

This report presents the results from the Environment Agency's monitoring of radioactivity in the environment during 1996. Monitoring programmes were carried out in support of the Agency's regulatory functions under the Radioactive Substances Act 1993 and as part of the UK Government's obligations under the Euratom Treaty. The programmes included: effluent monitoring; the quality checking of solid waste disposals; environmental monitoring; the monitoring of radioactivity in air and rainwater; the monitoring of radioactivity in drinking water sources. A total of 160 effluent samples were analysed for nearly 900 determinants, two consignments of solid radioactive waste destined for disposal at British Nuclear Fuels' site at Drigg were checked, direct instrumental monitoring was carried out at ISO locations within the vicinity of nuclear sites, and 532 environmental samples were analysed for over 2,000 determinants. Effluent monitoring: The Agency requires operators of certain sites to provide samples of their liquid effluents for independent analysis. The results are compared with reports submitted by site operators. The majority of results showed satisfactory agreement; operators' values were frequently higher than the Agency's measurements indicating that they were not under-reporting. However, some discrepancies were found and are being investigated. Quality checking of solid waste disposals: Consignments of solid low level radioactive waste are seized by inspectors for examination at the Agency's Waste Quality Checking Laboratory. Sophisticated non-destructive and destructive analytical techniques are used at the laboratory to check the radioactive content and description of the wastes. Consignments of waste from the Atomic Weapons Establishment at Aldermaston and Amersham International at Amersham were examined. In both cases the operators reported higher activity than the Agency's laboratory. The consignments also conformed with the operators' disposal

Impact of treated effluents released from processing of radioactive mineral on the aquatic environment of Periyar river

International Nuclear Information System (INIS)

Radhakrishnan, Sujata; Haridasan, P.P.; Radhakrishna Pillai, K.; Pillai, P.M.B.; Khan, A.H.

2005-01-01

The chemical processing of monazite/ thorium concentrate for the separation of thorium, uranium and rare earths results in the generation of effluents, both acidic and alkaline. Indian Rare Earths Ltd (IREL), Udyogamandal was carrying out processing of monazite for nearly 50 years. Presently (since 2004) Indian Rare Earths Ltd, Udyogamandal is processing earlier stocked thorium hydroxide concentrate retrieved from Silos to produce Thorium Oxalate (along with a small percentage of Rare Earth elements), Nuclear Grade Ammonium Di-Uranate (NGADU), and small quantities of Nuclear Grade Thorium Oxide ('THRUST' Project). The treated effluents after monitoring are discharged to river Periyar. River Periyar is the recipient water body for treated effluents from IREL as well as a host of other chemical industries. Indian Rare Earths Ltd, Udyogamandal had been carrying out chemical processing of monazite for the past 50 years. Recently, from 2004, the plant has shifted from monazite processing to processing of thorium concentrate (THRUST Project). The present paper discusses the characteristics of the effluents generated as per this project, their treatment, monitoring methodology, discharge and impact on the aquatic environment of river Periyar. It has been noted that the impact on the aquatic environment by way of enhancing the natural background radioactivity in the river had been insignificant. (author)

The use of PHP in the radioactive effluent treatment in rare earth industry

International Nuclear Information System (INIS)

Shitang, Q.; Ruensheng, W.

1985-01-01

Monazite is one of the most important rare earth resources, processing monazite, however, is accompanied by radioactive effluent that needs treatment. A satisfactory treatment should be able not only to insolubilize the radioactive isotopes but also to clarify the suspension quickly and completely. In this study, out of 15 different coagulants, partially hydrolyzed polyacrylamide (PHP) of molecular weight 1000 has been chosen as the most efficient one for the clarification of the treated effluent in question. Satisfactory performance has been attained in a continuous clarifier

Study about the integrated treatment of chemical and radioactive effluents, introducing the zero release concept

International Nuclear Information System (INIS)

Mierzwa, Jose Carlos

1996-01-01

An Integrated System to the treatment of Chemical and Radioactive Effluents to the Centro Experimental Aramar is proposed and evaluated, introducing the Effluent Zero Release concept, where factors related to the environmental regulation in vigor in the country, as well as the availability of hydrological resources in the place where CEA have been implanted, are considered. Through a literature analysis of the main effluents treatment techniques available nowadays and after a case of study selection, take into account two industrial installations that will be implanted at CEA, it was defined an arrangement to compose the Integrated System to the Treatment of Chemicals and Radioactive Effluents, focusing the Zero Release concept consolidation. A defined arrangement uses a combination among three treatment processes, it means chemical precipitation, reverse osmosis and evaporation, that were experimentally evaluated. The proposed arrangement was evaluated using synthetic effluents, that were prepared based on data from literature and conception documents of the installation considered in this work. Three kinds of effluents were simulated, one arising from a nuclear reactor laundry, one arising from the water refrigeration system and demineralized water production to the nuclear reactor and the other one arising from a nuclear material production laboratory. Each effluent were individually submitted to the selected treatment processes, to get the best operational conditions for each treatment process. The results got during the laboratory assays show that the proposed Integrated System to the Treatment of Chemicals and Radioactive Effluents is feasible, consolidating the Effluent Zero Release concept, which is the proposition of this work. (author)

Annual report on radioactive discharges and monitoring of the environment 1980

International Nuclear Information System (INIS)

1981-07-01

A report is given on radioactive discharges through authorised outlets and on environmental monitoring for all of British Nuclear Fuels Limited Works and Sites, i.e. the Windscale and Calder Works and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes information on liquid and airborne radioactive effluents and solid radioactive waste at each of the Company's Works and Sites. Assessments are made of maximum radiological exposures to individual members of the public expressed in terms of limits based on ICRP recommendations and in accordance with advice given by the NRPB. The report showed that at no time during 1980 did discharges and disposals of radioactive wastes through authorised outlets at any of the Works exceed those laid down in any of the Authorisations. Environmental monitoring studies also showed that the radiation exposure in 1980 of the most highly exposed groups of the general population was significantly lower than the Annual Limit recommended by the ICRP. (U.K.)

Siting considerations for radioactivity in reactor effluents during normal operation

International Nuclear Information System (INIS)

Graf, J.M.; Strom, P.O.

1975-01-01

In selecting a proper site for a nuclear power station, the consideration of radioactivity released in effluents can be handled in a straightforward manner using the U. S. Atomic Energy Commission's proposed Appendix I to 10 CFR 50, which gives numerical guidelines for design objectives for meeting the criterion ''as low as practicable'' for radioactive material in light-water-cooled nuclear power reactor effluents. By relating the release of radioactive material, the site meteorological conditions, and site boundary distance through appropriate dose models, the suitability of a given site can be determined. ''Rules of thumb'' for comparing anticipated releases to design objectives can be constructed for rapid assessment using the maximum permissible concentration values of 10 CFR 20 as dose factors. These rules of thumb tend to underpredict the allowed releases except in the case of radiocesium in liquids. For gaseous releases, these rules of thumb can be made up in convenient nomogram form for a quick assessment of allowed releases based on local site meteorological conditions. (U.S.)

Study of sample-detector assemblies for application to in-situ measurement of radioactivity in liquid effluents

International Nuclear Information System (INIS)

Pendharkar, K.A.; Narayanan Kutty, K.; Krishnamony, S.

1991-01-01

This paper describes the experimental investigations carried out on four different types of sample-detector assemblies with a view to determining their detection limits and relative merits for application to in-situ measurement of radioactivity in liquid effluents. The four systems studied were: (1) gamma detection using 11 cm x 8 cm NaI (Tl) scintillation detector inserted in the cavity of a specially designed stainless steel chamber of capacity 15 liters, (2) gamma detection using a metal-walled G.M. counter in a similar manner, (3) beta detection using twin thin-walled G.M. counters immersed in liquid, and (4) end window G.M. counter positioned above the liquid surface in a shallow tray. The design features of an in-line monitor employing a 11 cm x 8 cm NaI (Tl) detector used for the routine monitoring of beta gamma activity concentrations in the low level effluents of the Tarapur Fuel Processing Plant are described. (author). 1 tab

Regulatory review of releases from HIFAR of radioactive airborne effluent

International Nuclear Information System (INIS)

Westall, D.J.; Macnab, D.I.

1996-01-01

Full text: The Nuclear Safety Bureau (NSB) was set up by legislation in 1992 as an independent Commonwealth corporate body reporting to the Minister for Health and Family Services. Its functions include monitoring and reviewing the safety of nuclear plant owned or operated by the Australian Nuclear Science and Technology Organisation (ANSTO). The NSB sets requirements for authorisation of the operation of the HIFAR research reactor, and may impose restrictions and conditions on its operation. The authorisation for the operation of HIFAR includes a requirement for arrangements for the treatment, safe storage and disposal of solid, liquid and gaseous radioactive wastes from the reactor. The objective is to establish conditions which would ensure that radiation exposure to plant personnel and the public from radioactive wastes are within acceptable limits and that releases are maintained as low as reasonably achievable. The NSB has developed expectations based on international best practice, against which to review HIFAR's arrangements for satisfying the requirement and achieving the objective. Arrangements for the release of airborne radioactive effluent from HIFAR were reviewed by the NSB as part of an overall review of the upgrade of safety documentation for HIFAR. The NSB's expectations for the review were drawn from the International Atomic Energy Agency (IAEA) Basic Safety Standards (Safety Series No 115-I) and the National Health and Medical Research Council (NHMRC) Recommendations for Limiting Exposure to Ionizing Radiation (1995). These expectations included a hierarchy of primary dose limits, stack discharge limits and reference levels for HIFAR aimed at ensuring that radiation doses to the public due to airborne effluent are less than the national dose limits and ANSTO's dose constraints, and are as low as reasonably achievable. An approach favoured by the operator is to work directly to a primary dose limit using an airborne dispersion computer program to

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

Guide for effluent radiological measurements at DOE installations

International Nuclear Information System (INIS)

Corley, J.P.; Corbit, C.D.

1983-07-01

Effluent monitoring and reporting programs are maintained at all US Department of Energy (DOE) facilities that may: (1) discharge significant concentrations of radioactivity in relation to applicable standards, or (2) discharge quantities of radioactivity that have potential health and safety or other environmental significance. This Guide is intended to provide supplemental guidance to DOE Orders on methods, procedures, and performance criteria to bring more comparable rationale to DOE facility effluent measurement programs and promote compliance with applicable standards and provide the DOE Office of Operational Safety (OOS) and Operations Offices with an additional tool for evaluating effluent measurement programs at DOE facilities

Estimation of radioactive effluents dispersion from the nuclear power plants in Yugoslavia surrounding

International Nuclear Information System (INIS)

Vehauc, A.

1997-01-01

The computational method for atmospheric dispersion of radioactive effluents is applied to the nuclear power plants in Yugoslavia surrounding. On the basis of computation results, ground level concentrations and washout of radioactive nuclides on exposed Yugoslav territories during unfavourable meteorological conditions are estimated. (author)

Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

International Nuclear Information System (INIS)

Frazier, T.P.

1994-01-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans

Environmental radioactivity. Measurement and monitoring

International Nuclear Information System (INIS)

2009-11-01

The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

Waste monitoring system for effluents

International Nuclear Information System (INIS)

Macdonald, J.M.; Gomez, B.; Trujillo, L.; Malcom, J.E.; Nekimken, H.; Pope, N.; Bibeau, R.

1995-07-01

The waste monitoring system in use at Los Alamos National Laboratory's Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system

Treatment of radioactive effluents at the Boris Kidric Institute; Postupak sa radioaktivnim elementima u Institutu Boris Kidric

Energy Technology Data Exchange (ETDEWEB)

Bojovic, P; Drobnik, S; Popara, D [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

1964-10-15

The paper describes the origin, composition and activity of radioactive effluents at the Boris Kidric Institute, their collection at the places or origin, transport to the place of disposal and treatment of some smaller quantities. Special attention has been paid to effluents with short-lived isotopes produced in the Laboratory for radioactive isotope production (author)

Management Aspects of Implementing the New Effluent Air Monitoring Standard

International Nuclear Information System (INIS)

Glissmeyer, John A.; Davis, William E.

2000-01-01

The revision to ANSI/HPS N13.1,'Sampling and Monitoring Releases of Airborne Radioactive substances From the Stacks and Ducts of Nuclear Facilities,' went into effect in January 1999 - replacing the 1969 version of the standard. There are several significant changes from the old version of the standard. The revised standard provides a new paradigm where representative air samples can be collected by extracting the sample from a single point in air streams where the contaminants are well mixed. The revised standard provides specific performance criteria and requirements for the various air sampling processes - program structure, sample extraction, transport, collection, effluent and sample flow measurement, and quality assurance. A graded approach to sampling is recommended with more stringent requirements for stacks with a greater potential to emit. These significant changes in the standard will impact the air monitoring programs at some sites and facilities. The impacts on the air monitor design, operation, maintenance, and quality control processes are discussed.

Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

International Nuclear Information System (INIS)

Chen Xiaoqiu

2009-01-01

Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

Processing and monitoring liquid, radioactive effluents from the Wiederaufarbeitungsanlage Karlsruhe

International Nuclear Information System (INIS)

Hoehlein, G.; Huppert, K.L.; Winter, M.

1977-01-01

The Wiederaufarbeitungsanlage Karlsruhe (WAK) serves as a demonstration plant for the processing of highly-irradiated uranous oxide. The high active waste concentrates find interim storage at the WAK until they are solidified at a later stage. In contrast to this, the slightly- and the medium-active liquid wastes are transported to the decontamination facility of the Nuclear Research Centre Karlsruhe, where they are immediately processed. These liquid wastes contain about 1 per thousand of the activity inventary of the fuel elements processed. Monitoring of the radioactive waste water of the WAK is carried out by the Nuclear Research Centre's department radiation protection and safety. (orig.) [de

Effluent and environmental monitoring of Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

Pilgrim, T.; De Waele, C.; Gallagher, C. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Atomic Energy of Canada Limited's (AECL's) Environmental Protection Program has been gathering environmental monitoring data at its Chalk River Laboratories (CRL) for over 60 years. The comprehensive effluent and environmental monitoring program at CRL consists of more than 600 sampling locations, including the Ottawa River, with approximately 60,000 analyses performed on air and liquid effluent parameters each year. Monitoring for a variety of radiological and non-radiological parameters is regularly conducted on various media, including ambient air, foodstuff (e.g. milk, fish, garden produce, large game, and farm animals), groundwater, Ottawa River water and other surface water on and off-site. The purpose of the monitoring program is to verify that past and current radiological and non-radiological emissions derived from AECL operations and activities, such as process water effluent into the Ottawa River, are below regulatory limits and demonstrate that CRL operations do not negatively affect the quality of water on or leaving the site. In fact, ongoing program reports demonstrate that radiological emissions are well below regulatory limits and have been declining for the past five years, and that non-radiological contaminants do not negatively affect the quality of water on and off the site. Two updated Canadian Standards Association (CSA) standards for Effluent and Environmental monitoring have come into effect and have resulted in some changes to the AECL Program. This presentation will discuss effluent and surface water monitoring results, the observed trends, the changes triggered by the CSA standards, and a path forward for the future. (author)

Report on radioactive discharges and environmental monitoring at nuclear power stations during 1991

International Nuclear Information System (INIS)

Hurst, M.J.; Thomas, D.W.

1992-09-01

This report presents the details for 1991 of radioactive discharges and environmental monitoring at Nuclear Electric sites. In addition to the main section which summarises the discharges and monitoring at the Company's nuclear sites as a whole, appendices are presented covering the data in detail for individual sites. In each case the radiological impact on the general public has been estimated. Discharges generally were not substantially different from those of recent years. All radioactive effluent discharges from power stations were within authorised limits. Radiation doses to members of the public resulting from these discharges, and from direct radiation from the Stations, were in all cases less than the limit of 1 mSv per year which has been recommended by ICRP since 1985. (Author)

Effluent treatment plant and decontamination centre, Trombay

International Nuclear Information System (INIS)

Kaushik, C.P.; Agarwal, K.

2017-01-01

The Bhabha Atomic Research Centre, Trombay, has a number of plants and laboratories, which generate Radioactive Liquid Waste and Protective Wears. Two facilities have been established in late 1960s to cater to this requirement. The Centre, on the average generates about 50,000 m"3 of active liquid effluents of varying specific activities. The Effluent Treatment Plant was setup to receive and process radioactive liquids generated by various facilities of BARC in Trombay. It also serves a single-point discharge facility to enable monitoring of radioactive effluents discharged from the Trombay site. About 120-150 Te of protective wears and inactive apparel are generated annually from various radioactive facilities and laboratories of BARC. In addition, contaminated fuel assembly components are generated by DHRUVA and formerly by CIRUS. These components require decontamination before its recycle to the fuel assembly process. The Decontamination Centre, setup in late 1960s, is mandated to carry out the above mentioned decontamination activities

Continuous monitoring of gaseous effluents

International Nuclear Information System (INIS)

Velasco, A.; Giraut, H.; Prado, M.; Bonino, A.D.

1990-01-01

The system allows to continuously determine the radioactive materials discharge (iodine, noble gases and aerosols) to the environment. It consists in compelling, by a pump, a known and fixed fraction of the total flow and preserving the aerosols by a filter. The gas -now free from aerosols- traverses an activated carbon filter which keeps the iodine; after being free from aerosols and iodine, the effluent traverses a measurement chambers for noble gases which has a scintillator. (Author) [es

Principles for limiting releases of radioactive effluents into the environment

International Nuclear Information System (INIS)

1986-01-01

This publication is concerned with the subject of limiting releases of radioactive effluents during normal, controlled operation of nuclear installations. It does not deal with releases from accidents where it is only possible to limit exposures by intervention. In 1978 the IAEA published guidance on the concepts and principles for use by the competent authorities in setting limits for planned releases of radioactive material into the environment (Safety Series No. 45). This publication is a complete revision of Safety Series No. 45 and its Annex

Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960); Elimination par dilution d'effluents liquides faiblement radioactifs. Leurs consequences (1960)

Energy Technology Data Exchange (ETDEWEB)

Bovard, P; Candillon, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [French] Les centres nucleaires ont frequemment a resoudre des problemes poses par l'elimination de volumes importants d'effluents liquides faiblement radioactifs. Dans l'etat actuel des choses, la solution la plus utilisee consiste a rejeter ces effluents dans le reseau hydrographique de maniere a les diluer au maximum et abaisser ainsi leurs teneurs en isotopes radioactifs au-dessous des normes imposees par la Sante Publique. Cette technique necessite un controle systematique du reseau et de ses dependances et demande une connaissance approfondie des processus d'adsorption et de fixation. (auteur)

Liquid Effluent Monitoring Information System (LEMIS) System Construction

International Nuclear Information System (INIS)

Adams, R.T.

1994-01-01

The liquid effluent sampling program is part of the effort to minimize adverse environmental impact during the cleanup operation at the Hanford Site. Of the 33 Phase I and Phase II liquid effluents, all streams actively discharged to the soil column will be sampled. The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Construction document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

Annual environmental monitoring report, January-December 1984

International Nuclear Information System (INIS)

1985-03-01

Non-radioactive monitoring program involved: repair of a leaking waste paint and solvent tank, installation of a pretreatment facility for liquid effluents from a plating shop; and construction discharge. Radioactivity was monitored for air with comparisons to the average annual population dose from neutron radiation and tritium in the waste water effluents

Radiological consequences of radioactive effluents

International Nuclear Information System (INIS)

Clarke, R.H.

1979-01-01

A study of the differential radiological impact of the nuclear fuel cycle with and without plutonium recycle is being undertaken jointly by the National Radiological Protection Board and the Commissariat a l'Energie Atomique (CEA). A summary is given of the development of the methodology detailed in their first report to the Commission of the European Communities (CEC) (NRPB/CEA, A methodology for evaluating the radiological consequences of radioactive effluents released in normal operations. Luxembourg, CEC Doc. V/3011/75 EN (1979)). The Collective Effective Dose Equivalent Commitment was used in an attempt to assess the total health detriment. The application of the methodology within particular member states of the European Community has been discussed at seminars. Sensitivity analysis can identify the more important parameters for improving the accuracy of the assessment. (UK)

Radioactive Plumes Monitoring Simulator

International Nuclear Information System (INIS)

Kapelushnik, I.; Sheinfeld, M.; Avida, R.; Kadmon, Y.; Ellenbogen, M.; Tirosh, D.

1999-01-01

The Airborne Radiation Monitoring System (ARMS) monitors air or ground radioactive contamination. The contamination source can be a radioactive plume or an area contaminated with radionuclides. The system is based on two major parts, an airborne unit carried by a helicopter and a ground station carried by a truck. The system enables real time measurement and analysis of radioactive plumes as well as post flight processing. The Radioactive Plumes Monitoring Simulator purpose is to create a virtual space where the trained operators experience full radiation field conditions, without real radiation hazard. The ARMS is based on a flying platform and hence the simulator allows a significant reduction of flight time costs

Construction and calibration of a simple scintillation counter for monitoring radioactive gases in ducts

International Nuclear Information System (INIS)

Johnston, M.S.

1984-07-01

A report is given of the practical construction, laboratory calibration and simple-in-situ calibration check of scintillation detectors used for monitoring radioactive inert gases in gaseous effluents. The βγ-ray and γ-ray detectors are identical except for an absorber which is placed over the window of the γ-ray detector after calibration. The construction and calibration of both detectors is therefore identical. (author)

Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

International Nuclear Information System (INIS)

Ballinger, M.Y.; Shields, K.D.

1999-01-01

The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP

Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

Energy Technology Data Exchange (ETDEWEB)

Ballinger, M.Y.; Shields, K.D.

1999-04-02

The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP.

Optimizing Liquid Effluent Monitoring at a Large Nuclear Complex

International Nuclear Information System (INIS)

Chou, Charissa J.; Johnson, V.G.; Barnett, Brent B.; Olson, Phillip M.

2003-01-01

Monitoring data for a centralized effluent treatment and disposal facility at the Hanford Site, a defense nuclear complex undergoing cleanup and decommissioning in southeast Washington State, was evaluated to optimize liquid effluent monitoring efficiency. Wastewater from several facilities is collected and discharged to the ground at a common disposal site. The discharged water infiltrates through 60 m of soil column to the groundwater, which eventually flows into the Columbia River, the second largest river in the contiguous United States. Protection of this important natural resource is the major objective of both cleanup and groundwater and effluent monitoring activities at the Hanford Site. Four years of effluent data were evaluated for this study. More frequent sampling was conducted during the first year of operation to assess temporal variability in analyte concentrations, to determine operational factors contributing to waste stream variability and to assess the probability of exceeding permit limits. Subsequently, the study was updated which included evaluation of the sampling and analysis regime. It was concluded that the probability of exceeding permit limits was one in a million under normal operating conditions, sampling frequency could be reduced, and several analytes could be eliminated, while indicators could be substituted for more expensive analyses. Findings were used by the state regulatory agency to modify monitoring requirements for a new discharge permit. The primary focus of this paper is on the statistical approaches and rationale that led to the successful permit modification and to a more cost-effective effluent monitoring program

Radioactive effluent sources and special system of channels on the RA Reactor at the Boris Kidric Institute

International Nuclear Information System (INIS)

Bojovic, P.; Gacinovic, O.; Milosevic, M.

1964-10-01

The paper describes the place of origin, composition and activity of radioactive effluents appearing in some reactor systems and special channels for carrying these effluents to disposal basins located outside the reactor building (author)

Development of radioactive seawater monitors, 1

International Nuclear Information System (INIS)

Fukushima, Masanori

1989-01-01

Applicability of some adsorptive materials to monitoring of radioactive seawater is generalized. Studied techniques that allow utilization of adsorptive materials in monitoring radioactive seawater are the substitute methods using sampled seawater or indicator plants such as gulfweed and the method using adsorptive materials for continuous monitoring of underwater radioactivity, the method using them for field measurement of under water radioactivity from a boat, and the method using an adsorptive material moored underwater for integration monitoring of underwater radioactivity. Selected adsorptive materials that were judged suitable for monitoring radioactive seawater is the one composed of some kind of adsorptive compound (manganese dioxide or ferrocyan cobalt potassium) fixed to crylic cellulose. This adsorptive material permits selective scavenging radioactive Cs, Mn, Co, Zn, Ce, Fe, Ru, Ra Th, Pu and Am from seawater. (aurhor)

Consideration of radioecological studies in French regulations on the discharges of radioactive effluents

International Nuclear Information System (INIS)

Hebert, J.

1980-01-01

For each of the lines of approach of the regulations on radioactive effluent discharges utilized in France, the report examines the place of radioecology. Developments in greater depth will be devoted to the preliminary and definitive studies foreseen by the conditions of effluent discharges coming from the base nuclear facilities. The place of radioecology in general international law on pollution across national borders or of the sea will also be examined [fr

Treatment of radioactive effluents by concentration in an installation with natural evaporation

International Nuclear Information System (INIS)

Wormser, G.; Chauvet, P.

1963-01-01

This document reports natural evaporation tests performed in Cadarache, notably to adapt the equipment to the treatment of radioactive effluents. After a brief description of the apparatus principle and operation, the authors propose a summary of the first test campaign (test apparatus, results), indicate modifications brought to the apparatus by taking the first results into account, and propose a detailed discussion of results obtained during the second test campaign. They finally discuss the possibility of concentration of effluents by means of natural evaporation [fr

Monitoring of noble gas radioisotopes in nuclear power plant effluents

International Nuclear Information System (INIS)

Kabat, M.J.

1985-01-01

Monitoring of gaseous radionuclides in the effluents of nuclear facilities is an essential requirement in effluent management programs. Since there is no practical way of removing noble gas radioisotopes from air at release pathways, their accurate monitoring is essential for providing appropriate environmental protection. Emitted γ dose-rate is the limiting factor for concentration-time integral of noble gas in gaseous effluents of reactor facilities. The external exposure to the public from a semi-infinite cloud is directly proportional to both the noble gas isotope concentration and the integrated γ energy per disintegration. Both can be directly measured in gaseous effluent pathways with a suitable detector. The capability of NaI(T1), CaF 2 (Eu) and plastic scintillation detectors to measure the γ-Ci.MeV content of noble gas releases was experimentally evaluated. The combination of CaF 2 (Eu) detector in a pressurized through-flow chamber, with a charge integrating scaler well complied with both γ energy response and detection sensitivity requirements. Noble gas source terms and effluent monitoring criteria are discussed, theoretical and experimental results are presented and a practical, on-line noble gas monitoring system is described

Effluent treatment efficiency and compliance monitoring in Nigerian ...

African Journals Online (AJOL)

The effectiveness of effluent treatment at the Eleme Petrochemical Industry, Port Harcourt, Nigeria was monitored weekly for six weeks to assess their level of compliance with the Directorate of Petroleum Resources (DPR) guidelines and standards for environmental safety. Effluent samples were taken from the untreated ...

Assessment methodology for radioactive effluents

International Nuclear Information System (INIS)

Anon.

1977-01-01

The objective of this environmental assessment is to define and rank the needs for controlling radioactive effluents from nuclear fuel cycle facilities. The assessment is based on environmental standards and dose-to-man calculations. The study includes three calculations for each isotope from each facility: maximum individual dose for a 50-year dose commitment from a 1-yr exposure according to the organ affected; population dose for a 50-yr dose commitment from a 1-yr exposure according to the organ affected; and annual dose rate for the maximally exposed individual. The relative contribution of a specific nuclide and source to the total dose provides a method of ranking the nuclides, which in turn identifies the sources that should receive the greatest control in the future. These results will be used in subsequent tasks to assess the environmental impact of the total nuclear fuel cycle

Monitoring and management of tritium from the nuclear power plant effluent

Science.gov (United States)

Zhang, Qiaoe; Liu, Ting; Yang, Lili; Meng, De; Song, Dahu

2018-01-01

It is important to regulate tritium nuclides from the nuclear power plant effluent, the paper briefly analyzes the main source of tritium, and the regulatory requirements associated with tritium in our country and the United States. The monitoring methods of tritium from the nuclear power plant effluent are described, and the purpose to give some advice to our national nuclear power plant about the effluent of tritium monitoring and management.

Method for radioactivity monitoring

Science.gov (United States)

Umbarger, C. John; Cowder, Leo R.

1976-10-26

The disclosure relates to a method for analyzing uranium and/or thorium contents of liquid effluents preferably utilizing a sample containing counting chamber. Basically, 185.7-keV gamma rays following .sup.235 U alpha decay to .sup.231 Th which indicate .sup.235 U content and a 63-keV gamma ray doublet found in the nucleus of .sup.234 Pa, a granddaughter of .sup.238 U, are monitored and the ratio thereof taken to derive uranium content and isotopic enrichment .sup.235 U/.sup.235 U + .sup.238 U) in the liquid effluent. Thorium content is determined by monitoring the intensity of 238-keV gamma rays from the nucleus of .sup.212 Bi in the decay chain of .sup.232 Th.

Management of effluents and radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

2005-01-01

Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

Packaging of radioactive sludges at the Saclay effluent processing plant

International Nuclear Information System (INIS)

Cerre, Pierre; Mestre, Emile; Bourdrez, Jean; Leconnetable, Jean

1964-10-01

The authors describe technical and technological aspects of the packaging workshop for radioactive sludges produced by processes of co-precipitation of Saclay effluents. This facility is an achievement of studies which aimed at improving working conditions for the plant staff. This workshop implements a process of solidification of filtered sludge by mixing with a hydraulic binding agent. After some generalities on the decontamination process applied to effluents produced by the Saclay research centre, the authors present and describe the adopted process, propose a physical description of the facility: building, chemical engineering equipment (filtration, packaging, and handling). They describe facility operation: introduction of a block into the cell, block filling, output of a packaged container. They briefly discuss the first results of facility exploitation [fr

Effluent monitoring for nuclear safeguards

International Nuclear Information System (INIS)

Stanchi, L.

1977-01-01

A microprocessor-based instrument operates a continuous surveillance on effluents from a nuclear facility. It receives and evaluates pulses from two NaI detectors and a set of single-channel analyzers. It has self-diagnosing capability so that it takes actions not only when it recognizes excessive radioactivity but also when it ascertains some abnormal behavior. Power failure procedure and automatic restart are provided. Operative constants such as alarm thresholds, times, and number of successive measurements are permanently stored in a read/write battery operated C-MOS memory. The program allows automatic succession of phases in a peculiar way and has a feature for loading an auxiliary program into RAMs

Effluent monitoring for nuclear safeguards

International Nuclear Information System (INIS)

Stanchi, L.

1976-01-01

A microprocessor-based instrument operates a continuous surveillance on effluents from a nuclear facility. It receives and evaluates pulses from two NaI detectors and a set of single-channel analyzers. It has self-diagnosing capability so that it takes actions not only when it recognizes excessive radioactivity but also when it ascertains some abnormal behavior. Power failure procedure and automatic restart are provided. Operative constants such as alarm thresholds, times, and number of successive measurements are permanently stored in a read/write battery operated C-MOS memory. The program allows automatic succession of phases in a peculiar way and has a feature for loading an auxiliary program into RAMs

Investigations of the detection of α-radioactivity in samples of effluent water primary circuit and exhaust air of nuclear power plants in the FRG in the years 1973-1975

International Nuclear Information System (INIS)

Hoetzl, H.; Rosner, G.; Winkler, R.

1976-05-01

Since the middle of 1973 the α-radioactivity of aerosol filters from the stack monitoring system and since the middle of 1974 the α-radioactivity in samples from the primary cycle of the KRB was monitored. Effluent water samples of all nuclear power reactors of the FRG were also examined from the middle of 1973 till 1974. Furthermore, aerosol filters sampled in 1973 and 1974 from various places at the KRB and some aerosol filters from the stack monitoring systems of KWW (1973), KWO (1974) and KKS (1975) were also measured. Essentially, the following procedures of sample preparation for α-spectrometry of the samples in large-area gridded ionization chambers were used: cold ashing of the aerosol samples in 'excited' oxygen; coprecipitation of the alpha emitters from the effluent water samples with iron hydroxide and subsequent cold ashing of the precipitate; evaporation of the samples from the primary cycle on SS plates. The following transuranium nuclides, or some of them, were found in the samples of the primary coolant and in several aerosol filter samples: Pu-239/240, Pu-238 and/or Am-241, Cm-242 and Cm-244. Cm-242 contributes most to the α-radioactivity in fresh samples. In the effluent water samples Cm-242. Pu-239/240 and Pu-238 and/or Am-241 were identified in some cases, in one case also Cm-244. The aim of these investigations is to establish procedures for the measurement and surveillance of α-emitting nuclides in the emissions of power reactors in order to study the contribution of transuranium nuclides to the radiation exposure of the population living in the vicinity of nuclear power stations. (orig.) [de

Process and device for conditioning low and medium activity radioactive effluents with hydraulic binders

International Nuclear Information System (INIS)

Jaouen, C.; Magnin, G.; Renault, G.

1986-01-01

Chemical processing of borated radioactive effluents is claimed. Tetrahydrated calcium borate crystals are prepared by lime additions, the volume is reduced by evaporation under reduced pressure and the product obtained is mixed with hydraulic binders [fr

Optimizing liquid effluent monitoring at a large nuclear complex.

Science.gov (United States)

Chou, Charissa J; Barnett, D Brent; Johnson, Vernon G; Olson, Phil M

2003-12-01

Effluent monitoring typically requires a large number of analytes and samples during the initial or startup phase of a facility. Once a baseline is established, the analyte list and sampling frequency may be reduced. Although there is a large body of literature relevant to the initial design, few, if any, published papers exist on updating established effluent monitoring programs. This paper statistically evaluates four years of baseline data to optimize the liquid effluent monitoring efficiency of a centralized waste treatment and disposal facility at a large defense nuclear complex. Specific objectives were to: (1) assess temporal variability in analyte concentrations, (2) determine operational factors contributing to waste stream variability, (3) assess the probability of exceeding permit limits, and (4) streamline the sampling and analysis regime. Results indicated that the probability of exceeding permit limits was one in a million under normal facility operating conditions, sampling frequency could be reduced, and several analytes could be eliminated. Furthermore, indicators such as gross alpha and gross beta measurements could be used in lieu of more expensive specific isotopic analyses (radium, cesium-137, and strontium-90) for routine monitoring. Study results were used by the state regulatory agency to modify monitoring requirements for a new discharge permit, resulting in an annual cost savings of US dollars 223,000. This case study demonstrates that statistical evaluation of effluent contaminant variability coupled with process knowledge can help plant managers and regulators streamline analyte lists and sampling frequencies based on detection history and environmental risk.

Monitoring of radioactive wastes

International Nuclear Information System (INIS)

Houriet, J.Ph.

1982-08-01

The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements

Radioactivity monitoring in Romania

International Nuclear Information System (INIS)

Alexandrescu, M.; Milu, C.

1996-01-01

Radioactivity monitoring in Romania is based on National Regulations for Radiation Protection enforced in 1976, on other environment protection laws enforced in the last years and on the recommendations of IAEA. Accordingly two systems of radioactive monitoring are to date operational in this field: the first one is the self-control of the radioactive emissions in the environment generated by the own nuclear activities (of nuclear units like the Cernavoda NPP, the Institute of Atomic Physics at Magurele-Bucharest, the Institute for Nuclear Research at Pitesti, the R Plant at Feldioara, Uranium mining units, etc.), while the other is based on two national agencies (the National Network of Environment Radiation Monitoring of the Ministry of Waters, Forests and Environment Protection and the Network of Radiation Hygiene Laboratories of the Health Ministry). The authors review and discuss the radiation protection legislation, the structure and the organizational operations of the national monitoring systems and the co-operation of the national monitoring systems with international authorities or programmes. 3 Figs., 1 tab., 11 refs

Calculation of releases of radioactive materials in gaseous effluents from nuclear-powered merchant ships (NMS-GEFF code)

International Nuclear Information System (INIS)

Cardile, F.P.; Bangart, R.L.; Collins, J.T.

1978-06-01

The Intergovernmental Maritime Consultative Organization IMCO) is currently preparing guidelines concerning the safety of nuclear-powered merchant ships. An important aspect of these guidelines is the determination of the releases of radioactive material in effluents from these ships and the control exercised by the ships over these releases. To provide a method for the determination of these releases, the NRC staff has developed a computerized model, the NMS-GEFF Code, which is described in the following chapters. The NMS-GEFF Code calculates releases of radioactive material in gaseous effluents for nuclear-powered merchant ships using pressurized water reactors

Liquid Effluent Monitoring Information System test plans release 1.2

International Nuclear Information System (INIS)

Adams, R.T.

1994-01-01

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

Sellafield (release of radioactivity)

Energy Technology Data Exchange (ETDEWEB)

Cunningham, J; Goodlad, A; Morris, M

1986-02-06

A government statement is reported, about the release of plutonium nitrate at the Sellafield site of British Nuclear Fuels plc on 5 February 1986. Matters raised included: details of accident; personnel monitoring; whether radioactive material was released from the site; need for public acceptance of BNFL activities; whether plant should be closed; need to reduce level of radioactive effluent; number of incidents at the plant.

Liquid Effluent Monitoring Program at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Ballinger, M.Y.

1995-05-01

Pacific Northwest Laboratory (PNL) is conducting a program to monitor the waste water from PNL-operated research and development facilities on the Hanford Site. The purpose of the program is to collect data to assess administrative controls and to determine whether discharges to the process sewer meet sewer criteria. Samples have been collected on a regular basis from the major PNL facilities on the Hanford Site since March 1994. A broad range of analyses has been performed to determine the primary constituents in the liquid effluent. The sampling program is briefly summarized in the paper. Continuous monitoring of pH, conductivity, and flow also provides data on the liquid effluent streams. In addition to sampling and monitoring, the program is evaluating the dynamics of the waste stream with dye studies and is evaluating the use of newer technologies for potential deployment in future sampling/monitoring efforts. Information collected to date has been valuable in determining sources of constituents that may be higher than the Waste Acceptance Criteria (WAC) for the Treated Effluent Disposal Facility (TEDF). This facility treats the waste streams before discharge to the Columbia River

Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL)

International Nuclear Information System (INIS)

Ruiz C, M.A.; Rivero G, T.; Celis del Angel, L.; Sainz M, E.; Molina, G.

2006-01-01

Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote

Radioactive effluents from CANDU 6 reactors during normal operation

International Nuclear Information System (INIS)

Boss, C.R.; Allsop, P.J.

1995-12-01

During routine operation of a CANDU 6 reactor, various gaseous, liquid, and solid radioactive wastes are generated. The layout of the CANDU 6 reactor and the design of its systems ensure that these are minimized, but small quantities of gaseous and liquid wastes are continually discharged at very low concentrations. This report discusses the make-up of these chronically generated gaseous and liquid effluents. From a safety perspective, the doses to individual members of the public resulting from radioactive wastes chronically discharged from CANDU 6 reactors have been negligible. Similarly, doses to the regional and global populations have been negligible, generally less than 0.001% of background. While far below regulatory limits, releases of tritium, noble gases and gross β - -γ have been the most radiologically significant emissions, while radioiodine and particulates have had the greatest potential to deliver public dose. (author). 8 refs., 16 tabs., 3 figs

Fenceline water quality monitoring of effluents from BARC establishment

International Nuclear Information System (INIS)

Prathibha, P.; Kothai, P.; Saradhi, I.V.; Pandit, G.G.; Puranik, V.D.

2007-01-01

Wastewater generated from various sources (industrial, residential, rain water runoff etc.,) is either discharged into water bodies or reused/recycled for various purposes. Continuous monitoring of the wastewater is necessary to check whether these effluents are meeting the stringent limits proposed for discharge into water bodies or recycled/reused. Monitoring of these effluents also helps in designing the wastewater treatment system required to meet the standards. In this paper, water quality monitoring carried out during each quarter of the year 2005 for the effluents discharged from different utilities of BARC into Trombay bay is presented. The results indicate that the Bio-chemical oxygen demand (BOD) and chemical oxygen demand (COD) are in the range of 7.9 to 38.9 mg/l and 29.4 to 78.9 mg/l respectively. The nitrates and sulphates are in the range of 0.5 to 7.2 mg/l and 7.8 to 52.3 mg/l respectively. The water quality data of the parameters analyzed are well within the limits stipulated by Central Pollution Control Board. (author)

IRSN's expertise about nuclear medicine hospital effluents

International Nuclear Information System (INIS)

2009-01-01

This brief note aims at presenting the radioactivity follow up of hospital effluents performed by the French Institute of Radiation Protection and Nuclear Safety (IRSN). This follow up concerns the radioactive compounds and radiopharmaceuticals used in nuclear medicine, and principally technetium 99 and iodine 131. The IRSN has developed a network of remote measurement systems for the monitoring of sewers and waste water cleaning facilities. Data are compiled in a data base for analysis and subsequent expertise. (J.S.)

Control verification radioactive effluent discharges to the environment

International Nuclear Information System (INIS)

Alvarez, D.E.; Czerniczyniec, M.A.; Amado, V.A.; Curti, A.R.; Lee Gonzáles, H.M.

2015-01-01

The National Law of Nuclear Activity No. 24,804 establishes that the Nuclear Regulatory Authority (ARN) will be responsible for the function of regulation and control of nuclear activity, grant, suspend and revoke licenses, permits or authorizations and to issue regulatory standards on radiation and nuclear safety. According to the latter the ARN has issued a set of rules that make up the regulatory framework for nuclear activity. This includes the standards that determine the radiological criteria for controlling the release of radioactive effluents which were established to protect members of the public. In the process of licensing a facility, the ARN determines the authorized discharge of gaseous and liquid effluents which must comply with the installation values. These annual values are understood as an operating restriction (OR) and arise from the activity of each relevant radionuclide present in the discharge. For this is taken as a reference the level of optimized discharge considering an appropriate margin of flexibility to ensure public protection without interfering with the operation of the installation. This paper presents the results of the review of the above criteria and methodology for calculating the RO adopted by the RNA present. [es

Calibration of new measuring systems to detect emissions of radioactive noble gases

International Nuclear Information System (INIS)

Winkelmann, I.; Kreiner, H.J.

1977-12-01

This report describes the calibration of different systems for the integral measurement of radioactive noble gases and the calibration of a measuring chamber for the detection of individual nuclides of radioactive noble gases in the gaseous effluent of nuclear power plants. For these measuring chambers the calibration factors for Kr-85 and Xe-133 are given as well as the detection limits to be obtained with these measuring systems for several radioactive noble gases present in the gaseous effluent at the stack of nuclear power plants. Calibration factors for Kr-85 and Xe-133 and the detection limits of this measuring method for the detections of individual nuclides of radioactive noble gases in air samples are defined taken wirh a high pressure compressor in pressure flasks an measured on a Ge(Li)-semiconductor spectrometer (pressure flask measuring method). A measuring equipment is described and calibrated which allows simultaneous measurement of activity concentration of radioactive noble gases and radioactive aerosols with a sensitivity of 2 x 10 -7 Ci/m 3 for radioactive gases and 1 x 10 -9 Ci/m 3 for radioactive particulates at a background radiation of 1 R/h. This paper is an additional report to our STH-Bericht 3/76, 'Calibration of measuring equipment for monitoring of gaseous effluents from nuclear power plants', which specifies a procedure for the calibration of measuring chambers for monitoring of gaseous radioactive effluents from nuclear power plants /1/. The calibration system used here makes it possible to simultaneously calibrate several noble gas measuring devices. (orig.) [de

Environmental monitoring report: Sandia Laboratories, 1976

International Nuclear Information System (INIS)

Simmons, T.N.

1977-04-01

Water and vegetation are monitored to determine Sandia Laboratories impact on the surrounding environment. Nonradioactive pollutants released are reported. Radioactive effluents are also reported and their person-rem contribution to the Albuquerque population is calculated. The environmental monitoring for calendar year 1976 shows that concentrations of radioactive materials in the Albuquerque area are typical of natural background for the area. An exception is a single onsite location where slightly abnormal uranium concentrations are expected. An estimated 0.044 person-rem Albuquerque area (80 km radius) population dose commitment results from calculated Sandia Laboratories releases. Over the same area 57,000 person-rem is accumulated from natural background. There were no measurable offsite radioactive effluent releases in CY 1976

Liquid Effluent Monitoring Information System (LEMIS) test plans release 1.0

International Nuclear Information System (INIS)

Adams, R.T.

1994-01-01

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

Liquid Effluent Monitoring Information System (LEMIS) test plans release 1.1

International Nuclear Information System (INIS)

Adams, R.T.

1994-01-01

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

Realization of sanitary requirements concerning standardization of rare radioactive gas effluents at NPPs

International Nuclear Information System (INIS)

Doroshenko, G.G.; Panchenko, S.V.; Chudajkin, O.G.

1987-01-01

The paper is aimed at determination of ways for practical realization of main sanitary requirements concerning environment and population protection under NPP operation. The idea of the requirements is reduced to not increasing permissible limits for radiation doses, minimum irradiation of population and decrease of unjustified irradiation of personnel. The given problem may be fully solved only in case of studying real chacteristics of operating reactors, taking into account statistic nature of effluents of inert radioactive gases (IRG). Methods of developing a system of working and reference standards of IRG effluents at NPPs are suggested. The considered approach may be realized in practice as the All-Union state on branch standards

A radioactive noble gas quantitative analysis of gaseous effluents from NPP

International Nuclear Information System (INIS)

Yanev, Y.; Georgiev, K.; Mavrodiev, V.; Kikarin, B.

1993-01-01

The radioactive isotopes of argon, krypton and xenon comprise a substantial part of the gaseous emission of a NPP. A quantitative determination of their specific activity in the controlled area and the gaseous effluents requires a special sampling technique, as well as measurement method. The zeolites and the activated charcoals have a differentiated behaviour towards radioisotopes of argon, krypton and xenon. The isotope fractionation is often a problem, especially with argon and xenon. Some additional difficulties arise due to the irreproductibility of temperature and atmospheric moisture. The present paper describes a method for a spectrometric determination of radioactive noble gases after the cryogenic sampling developed at the Radiochemical laboratory of the Sofia University. The quality control of the method, as well as some special difficulties in its performing are discussed. The estimated minimum detectable activity is 5-10 Bq/m 3 for radioactive noble gases with half-life > 1 hour and sampling time for (resp. gamma-spectrometry) 1 hour. (author)

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

Energy Technology Data Exchange (ETDEWEB)

None

2000-12-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations.

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

International Nuclear Information System (INIS)

2000-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations

Occupational radiation protection experience in radioactive waste management at Bhabha Atomic Research Centre, Trombay, Mumbai, India

International Nuclear Information System (INIS)

Ramchandran, V.; Jauhri, G.S.

2000-01-01

Waste Management Facilities, Trombay (WMFT) comprises Radioactive Solid waste Management Site (RSMS), an Effluent Treatment Plant (ETP), and a Decontamination Centre (DC). Radioactive wastes from the plants and laboratories in Mumbai are handled here. The wastes are categorized and classified as per International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) guidelines. RSMS is a near surface disposal facility, where assorted beta gamma solid waste is disposed off in appropriate disposal facilities. ETP is a centralized low level liquid waste treatment facility, where liquid effluent is chemically treated to remove the radionuclides present in it, monitored for radioactivity, and discharged into the Mumbai Harbour Bay. In DC, plant and laboratory used clothings and personnel protective wears are decontaminated, monitored and sent for reuse. A comprehensive radiation monitoring programme is in place in these facilities from the beginning of radioactive waste management operations at BARC. The per capita radiation dose of the occupational workers and individual maximum dose has been low. Radioactivity release through liquid effluent from ETP has been kept well below Authorized Limits (AL). There has been no safety related unusual occurrences during the facility operation, that had any significant radiological impact. (author)

Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant; Predviduvanje na koncentraciite na radioaktivni aerozagaduvaci vo okolinata na nuklearni energetski postrojni

Energy Technology Data Exchange (ETDEWEB)

Arsov, Lj [Elektrostopanstvo, Skopje (Yugoslavia)

1977-07-01

This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

Environmental radioactivity. Measurement and monitoring; Umweltradioaktivitaet. Messung und Ueberwachung

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

Characterization and consequences from CEA nuclear fuel cycle facilities effluents releases - 1995 up to 2007 period

International Nuclear Information System (INIS)

Ferreira, Nelson Luiz Dias; Fonseca, Lizandra Pereira de Souza

2009-01-01

Discharges to the environment of airborne and/or liquid radioactive effluents from the normal operation of nuclear facilities can become a potential source of radiation exposure to humans. The highest exposed members of the public are defined as the critical group. The requirements for the control and monitoring of radioactive discharges to the environment and the degree of environmental monitoring required are linked to the assessed critical group dose. The assessed dose can be compared to dose constraint, which is a fraction of the annual effective dose to members of the public, as well as the level of exemption specified by the National Commission for Nuclear Energy (CNEN). Effluents releases from the Centro Experimental Aramar (CEA) facilities are registered and described at CEA Effluent Report, semestrally sent to CNEN. Basically, that report provides information related to the type and the quantity of chemical and radioactive substances released to the environment due the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). CEA Annual Effluent Report includes assessment of the annual effective doses for members of the critical group for the CEA site. This work presents the characterization of the radioactive release source terms and a historical of the critical group annual doses from 1995 up to 2007. (author)

Measurement of liquid radioactive materials for monitoring radioactive emissions

International Nuclear Information System (INIS)

1977-10-01

This draft regulation applies to measuring equipment for liquid radioactive materials for the monitoring of the radioactive discharges from stationary nuclear power plants with LWR and HTR reactors. Demands made on the measuring procedure, methods of concentration determination, balancing, indication of limiting values, and inspections are layed down. The draft regulation deals with: 1) Monitoring liquid radioactive discharges: Water and similar systems; radionuclides and their detection limits, radioactively contaminated water (waste water); secondary cooling water; power house cooling water; primary cooling water; flooding water; 2) Layout of the measuring and sampling equipment and demands made on continuous and discontinuous measuring equipment; demands made on discontinuous α and β measuring equipment; 3) Maintenance and repair work; inspections; repair of defects; 4) Demands made on documentation; reports to authorities; 5) Supplement: List of general and reference regulations. (orig./HP) [de

Environmental monitoring at the Lawrence Livermore National Laboratory. 1981 annual report

International Nuclear Information System (INIS)

Auyong, M.; Griggs, K.S.; Buddemeier, R.W.

1982-01-01

This report gives methods and results of the 1981 radiation monitoring program at LLL for both radioactive and non-radioactive contamination from gaseous and liquid effluents. Off-site monitoring includes various radionuclides but especially tritium in the ecosystems

Calculation of releases of radioactive materials in gaseous and liquid effluents from boiling water reactors (BWR-GALE Code)

International Nuclear Information System (INIS)

Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

1978-12-01

The calculational procedures described in the report reflect current NRC staff practice. The methods described will be used in the evaluation of applications for construction permits and operating licenses docketed after January 1, 1979, until this NUREG is revised as a result of additional staff review. The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment

Radioactive surface contamination monitors

International Nuclear Information System (INIS)

Aoyama, Kei; Minagoshi, Atsushi; Hasegawa, Toru

1994-01-01

To reduce radiation exposure and prevent contamination from spreading, each nuclear power plant has established a radiation controlled area. People and articles out of the controlled area are checked for the surface contamination of radioactive materials with surface contamination monitors. Fuji Electric has repeatedly improved these monitors on the basis of user's needs. This paper outlines typical of a surface contamination monitor, a personal surface contamination monitor, an article surface contamination monitor and a laundry monitor, and the whole-body counter of an internal contamination monitor. (author)

Operability test procedure for the TK-900 effluent monitoring station

International Nuclear Information System (INIS)

Weissenfels, R.D.

1994-01-01

This procedure will verify that the 221-B liquid effluent monitoring system, installed near the east end of the 6-in. chemical sewer header, functions as intended by design. TK-900B was installed near stairwell 3 in the 221-B electrical gallery by Project W-007H. The system is part of BAT/AKART for the BCE liquid effluent system

Substantiation of the radiation monitoring scope in the region of nuclear power plant location

Energy Technology Data Exchange (ETDEWEB)

Zykova, A S; Zhakov, Yu A; Yambrovskii, Ya M

1977-12-01

To provide radiation safety of the population in the region of nuclear power plant location, it is necessary to define the character and quantity of radiation monitoring. On the basis of radiation monitoring of effluents from operating nuclear power plants it is found that the effluents can be registered at a distance of 5-7 km from the plant. The quantity of sample analysis of the main enviromental objectives must provide an exact definition of the content of radioactive substances produced by radioactive fallouts and effluents from nuclear power plants.

Proceedings of the technical meetings 'Water, radioactivity and environment'

International Nuclear Information System (INIS)

Perceval, Olivier; Foulquier, Luc; Canneva, Guillem; Jedor, Beatrice; Genthon, Benedicte; Vicaud, Alain; Skrzypczak, Julien; Gibeaux, Audrey; Phrommavanh, Vannapha; Descostes, Michael; Tognelli, Antoine; Calmet, Dominique; Leprieur, Fabrice; Pignol, David; Thybaud, Eric; Feray, Christine; Leclerc, Elisabeth; Maitre, Melanie; Calmon, Philippe; Marang, Laura; Beaugelin-Seiller, Karine; Garnier-Laplace, Jacqueline; Leprieur, Fabrice; Philippot, Benoit; Hemidy, Pierre-Yves; Devin, Patrick; Perrier, Gilles; CALVEZ, Marianne; Descamps, E.; Preveral, S.; Brutesco, C.; Ginet, N.; Escofier, C.; Garcia, D.; Pignol, D.; Ansaldi, M.; Rodrigue, A.; Bazin, I.; Cholat, P.; Bailly-Du-Bois, Pascal; Fievet, Bruno; Godinot, Claire; Eyrolle-Boyer, Frederique; Antonelli, Christelle; Tournieux, Damien; Augeray, Celine; Galliez, Kevin; Baconet, I.; Cavaliere, N.; Dias Varela, D.; Foulon, L.; Laconici, C.; Lorand, H.; Mouton, M.; Siscard, N.; Tarlette, L.; Loyen, Jeanne; Gleizes, Marc; Vidal, R.; Borgia, Cecile; Hemidy, Pierre-Yves; Fouchet, Loic; Gontier, G.; Grignard, G.; Drozdzak, Jegodz; Leermakers, Martine; Brun, Frederic; Ameon, Roselyne; Gleizes, Marc; Maulard, Alain; Moine, Jerome; Tchilian, Nathalie; Paillard, Herve; Gaid, Abdelkader; Wittmann, Erich; Boucherie, Christophe; Devin, Patrick

2014-12-01

These technical days were organized by the 'Environment section' of the French Society of Radiation Protection (SFRP). Their aim was to review the current state of water use, management and monitoring, in particular in the nuclear industry, both on the radiological and chemical aspects. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Environmental issues linked to water and aquatic ecosystems contamination by micropollutants (O. Perceval); 2 - 50 years of radioecology in aquatic environments (L. Foulquier); 3 - Regulation and organisation of the French administration for water and aquatic ecosystems management (G. Canneva); 4 -European and French regulations about the radiological quality of drinking water (B. Jedor); 5 - Water samplings and liquid effluents from nuclear facilities: regulation, authorisations, prescriptions (B. Genthon); 6 - Water needs of a NPP (A. Vicaud); 7 - Water management at old uranium mining sites (A. Gibeaux); 8 - Mobile system for liquid effluents treatment (J. Skrzypczak); 9 - Water: an essential vector for the transfer of radioactive and chemical compounds in the underground (A. Tognelli); 10 - Environmental guide values for aquatic ecosystems protection (E. Thybaud); 11 - Prioritisation work for radioactive and chemical compounds to be monitored in aquatic environments in the framework of the environment perennial lab (E. Leclerc); 12 - Liquid radioactive effluents in continental aquatic environments: why and how estimating the impact? (K. Beaugelin-Seiller); 13 - Sustainable water management: standards, a compulsory tool (D. Calmet); 14 - Water sampling: from theory to practice (F. Leprieur, B. Philippot); 15 - Prototype for the detection of toxic compounds in the environment (D. Pignol); 16 - Nuclear metrology and water: new available and developing techniques (C. Augeray, K. Galliez); 17 - Measurement of the uranium and radium bio

Effluent and water treatment at AERE Harwell

International Nuclear Information System (INIS)

Lewis, J.B.

1977-01-01

The treatment of liquid wastes at Harwell is based on two main principles: separation of surface water, domestic sewage, trade wastes and radioactive effluents at source, and a system of holding tanks which are sampled so that the appropriate treatment can be given to any batch. All discharges are subject to independent monitoring by the authorising departments and the Thames Water Inspectors. (author)

Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents

International Nuclear Information System (INIS)

Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

1962-01-01

The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [fr

Radioactive liquid effluent management - state of art and the role of membrane processes

International Nuclear Information System (INIS)

Panicker, S.T.; Prabhakar, S.; Misra, B.M.; Ramani, M.P.S.

1990-01-01

This report reviews the conventional methods involving filtration, chemical precipitation, evaporation and ion exchange, employed for the treatment of low level radioactive effluents. The role of membrane processes, particularly reverse osmosis and ultrafiltration has been assessed with a view to increase the effectiveness of the existing methods. After overviewing the practices followed in major countries, a possible scheme has been proposed. (author). 66 refs., 4 tabs., figs

1985 environmental monitoring report

Energy Technology Data Exchange (ETDEWEB)

Day, L.E.; Miltenberger, R.P.; Naidu, J.R. (eds.)

1986-04-01

The environmental monitoring program is designed to determine that BNL facilities operate such that the applicable environmental standards and effluent control requirements have been met. The data were evaluated using the appropriate environmental regulatory criteria. The environmental levels of radioactivity and other pollutants found in the vicinity of BNL during 1985 are summarized in this report. Detailed data are not included in the main body of the report, but are tabulated and presented in Appendix D. The environmental data include external radiation levels; radioactive air particulates; tritium concentrations; the amounts and concentrations of radioactivity in and the water quality of the stream into which liquid effluents are released; the water quality of the potable supply wells; the concentrations of radioactivity in biota from the stream; the concentrations of radioactivity in and the water quality of ground waters underlying the Laboratoy; concentrations of radioactivity in milk samples obtained in the vicinity of the Laboratory; and the 1984 strontium-90 data which was not available for inclusion in the 1984 Environmental Monitoring Report. In 1985, the results of the surveillance program demonstraed that the Laboratory has operated within the applicable environmental standards.

Industrial effluent quality, pollution monitoring and environmental management.

Science.gov (United States)

Ahmad, Maqbool; Bajahlan, Ahmad S; Hammad, Waleed S

2008-12-01

Royal Commission Environmental Control Department (RC-ECD) at Yanbu industrial city in Kingdom of Saudi Arabia has established a well-defined monitoring program to control the pollution from industrial effluents. The quality of effluent from each facility is monitored round the clock. Different strategic measures have been taken by the RC-ECD to implement the zero discharge policy of RC. Industries are required to pre-treat the effluent to conform pretreatment standards before discharging to central biological treatment plant. Industries are not allowed to discharge any treated or untreated effluent in open channels. After treatment, reclaimed water must have to comply with direct discharge standards before discharge to the sea. Data of industrial wastewater collected from five major industries and central industrial wastewater treatment plant (IWTP) is summarized in this report. During 5-year period, 3,705 samples were collected and analyzed for 43,436 parameters. There were 1,377 violations from pretreatment standards from all the industries. Overall violation percentage was 3.17%. Maximum violations were recorded from one of the petrochemical plants. The results show no significant pollution due to heavy metals. Almost all heavy metals were within RC pretreatment standards. High COD and TOC indicates that major pollution was due to hydrocarbons. Typical compounds identified by GC-MS were branched alkanes, branched alkenes, aliphatic ketones, substituted thiophenes, substituted phenols, aromatics and aromatic alcohols. Quality of treated water was also in compliance with RC direct discharge standards. In order to achieve the zero discharge goal, further studies and measures are in progress.

Effluent releases at the TRIGA reactor facility

Energy Technology Data Exchange (ETDEWEB)

Whittemore, W L [General Atomic Co., San Diego, CA (United States)

1974-07-01

The principal effluent from the operating TRIGA reactors in our facility is argon-41. As monitored by a recording gas and particulate stack monitor, the values shown in the table, the Mark III operating 24 hours per day for very long periods produced the largest amount of radioactive argon. The quantity of 23.7 Ci A-41 when diluted by the normal reactor room ventilation system corresponded to 1.45 x 10{sup -6} {mu}Ci/cc. As diluted in the roof stack stream and the reactor building wake, the concentration immediately outside the reactor building was 25% MPC for an unrestricted area. The continued dilution of this effluent resulted in a concentration of a few percent MPC at the site boundary (unrestricted area) 350 meters from the reactor. (author)

Graphic overview system for DOE's effluent and environmental monitoring programs

International Nuclear Information System (INIS)

Burson, Z.G.; Elle, D.R.

1980-03-01

The Graphic Overview System is a compilation of photos, maps, overlays, and summary information of environmental programs and related data for each DOE site. The information consists of liquid and airborne effluent release points, on-site storage locations, monitoring locations, aerial survey results, population distributions, wind roses, and other related information. The relationships of different environmental programs are visualized through the use of colored overlays. Trends in monitoring data, effluent releases, and on-site storage data are also provided as a corollary to the graphic display of monitoring and release points. The results provide a working tool with which DOE management (headquarters and field offices) can place in proper perspective key aspects of all environmental programs and related data, and the resulting public impact of each DOE site

A study of effluent control technologies employed by radiopharmaceutical users and suppliers

International Nuclear Information System (INIS)

Leventhal, L.; Slider, J.; Chakoff, E.; Cehn, J.I.; Savage, E.

1980-01-01

The radiopharmaceutical industry facilities in the U.S.A. have been reviewed to identify factors that could lead to the airborne release of radioactive isotopes, and to assess the control technology employed. The subject is dealt with in brief outline under the following headings: 1) Hospital usage, the radionuclides being grouped according to use. The main potential airborne effluents were 131 I, 133 Xe, and sup(99m)Tc. 2) Monitoring of facilities for airborne effluents. 3) Control technology, either by dilution or by storage to reduce radioactivity; suppliers and users effluent controls. It was found that the control equipment is readily available, reliable, and effective. Cost appears to increase proportionately with the dose reduction provided. NRC requirements and cost-benefit ratios determine choice. It was concluded that current practices in the industry are adequate. (U.K.)

Studies on osmotic concentration of radioactive effluents

International Nuclear Information System (INIS)

Thomas, K.C.; Ramachandhran, V.; Misra, B.M.

1986-01-01

The potential of direct osmosis for concentrating radioactive effluents is examined on the laboratory scale. Studies were carried out using asymmetric cellulose acetate membranes of a range of porosities under varying salinity gradients. A suitable bench scale osmotic concentrator employing tubular membrane systems has been fabricated and tested. An attempt to understand the mechanism of water permeation under osmotic and hydrostatic gradients has been made based on the irreversible thermodynamic approach. The solute separation of sodium chloride and radionuclides under osmosis is in the range of 85 to 95% for various osmotic sink solutions. The osmotic water flux is observed to be lower than the hydraulic water flux under reverse osmosis conditions. While the solute separation increases with an increase in annealing temperature, water flux decreases for both osmosis and reverse osmosis systems for various feed salinities. The effect of concentration polarization is analysed, and the effect of feed and osmotic sink velocity on the performance of the osmotic concentrator has also been studied. (orig.)

Discussion on monitoring items of radionuclides in influents from nuclear power plants

International Nuclear Information System (INIS)

Zhang Yanxia; Li Jin; Liu Jiacheng; Han Shanbiao; Yu Zhengwei

2014-01-01

For the radionuclide monitoring items of effluents from nuclear power plant, this paper makes some comparisons and analysis from three aspects of the international atomic energy general requirements, the routine radionuclide measurement items of China's nuclear power plant and effluents low level radionuclide experimental research results. Finally, it summarizes the necessary items and recommended items of the radionuclide monitoring of effluents from nuclear power plant, which can provide references for the radioactivity monitoring activities of nuclear power plant effluent and the supervisions of regulatory departments. (authors)

Monitoring of radioactivity in drinking water

International Nuclear Information System (INIS)

Legarda, F.; Herranz, M.; Letessier, P.

2008-01-01

Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs

Handbook of radioactivity measurements procedures. Second edition

International Nuclear Information System (INIS)

Anon.

1985-01-01

This report is concerned with the measurement of radioactivity in general, but specifically it deals with radioactive materials that have become available in the last three decades, from nuclear reactors and particle accelerators, for applications in medicine, scientific research, and industry. It is also concerned with low-level radioactivity measurements for the monitoring of radioactivity in environmental media, such as air and water, in connection with the control of radioactive effluents associated with the production of nuclear power or the use of radionuclides. Included in appendices are nuclear decay data for selected radionuclides and statistics of radioactive decay. An extensive bibliography is also included

Radiation protection requirements in the limitation of the release of radioactive effluents

International Nuclear Information System (INIS)

Beninson, D.

1978-01-01

The paper summarizes the requirements of radiation protection, as presented in the new ICRP recommendation, in relation to the limitation of the release of radioactive effluents. The concepts of effective dose equivalent and collective dose equivalent are used in the presentation of the optimization procedures and the dose limitation to individuals. The dose commitment is used for the procedures applied to control future exposures. An appendix describes the basic concepts and quantities used in assessments of human exposures and risks. (author)

Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

International Nuclear Information System (INIS)

1997-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Zang Kual; Kang, Tae Woo [Jeju National Univ., Jeju (Korea, Republic of)

2000-12-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2000. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters. There was no significant difference in environmental radioactivities between 1999 and 2000.

Liquid Effluent Monitoring Information System test plans releases 2.0 and 3.0

International Nuclear Information System (INIS)

Guettler, D.A.

1995-01-01

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

Radioactive monitoring of the marine environment

International Nuclear Information System (INIS)

Bologa, A. S.

1991-01-01

Radioactivity monitoring of marine environment was required by the development of nuclear power and the worldwide use of ionizing radiations in many different activities. Both natural and artificial radioactivity play an important role in marine ecology and human health. In respect of this, three major facts prevail, namely: the fallout, the proximity of Danube River and the future nuclear power production. Spatial and temporal monitoring of marine radioactivity along the Romanian Black Sea shore has been systematically performed in Romanian Marine Research Institute in close cooperation with Institute of Meteorology and Hydrology since 1981. Marine emerged and submerged sediments, coastal and offshore sea water, macroalgae, invertebrates and fish of Danube mouths and/or along the coast are monitored for natural and artificial radioactivity by means of gross beta measurements and gamma spectrometry. Concentrations of radionuclides such as: K-40, Cs-134 and Cs-137 in abiotic and biotic samples, environmental distribution coefficients and concentration factors (CFs) as well as experimentally derived CFs in marine biota as radioecological bioindicators are assessed and stored in a national data base. (author)

Monitoring of environmental radioactivity

International Nuclear Information System (INIS)

1986-01-01

The results are described of monitoring radioactivity of atmospheric fallout, surface waters, soils, plant feeds, cereals, and other agricultural produce. The results were obtained over a long time period. Radioactivity was also measured of milk, milk products, vegetables and fruits, meat and hen eggs, flour and bakery products with a view to radionuclide migration in the food chain. The daily intake of 90 Sr and 137 Cs from food was determined from the values obtained and the consumption of the individual types of food. Strontium-90 distribution was studied in the bones and the teeth of the population in Slovakia. With the commissioning of nuclear power plants, emissions and liquid wastes were monitored and their environmental impact assessed. (E.S.)

The Use of Aquatic Macrophyte Ecotoxicological Assays in Monitoring Coastal Effluent Discharges in Southern Australia

Energy Technology Data Exchange (ETDEWEB)

Burridge, T.R.; Karistianos, M.; Bidwell, J

1999-01-01

Germination inhibition of zoospores of the aquatic, brown algal macrophyte Ecklonia radiata was employed to assess the toxicity of sewage effluents under short to long term exposure and under modified salinity conditions. The rate of germination inhibition was determined for exposure times between 2 and 48 h in salinity modified and unmodified regimes and under reduced salinity conditions alone. The results indicated that rate of germination inhibition increased with duration of exposure to sewage effluents and to salinity reduction alone, and that response to the effluents may be enhanced under conditions of reduced salinity. Whilst the effect of primary treated effluent was primarily that of toxicity, secondary treated effluent effects appeared to be primarily that of reduced salinity although at a greater rate than would be expected for salinity reduction alone. The assay is suggested to provide a mechanism for monitoring sewage effluent quality and to monitor potential impacts of sewage effluent discharge on kelp communities in southern Australia.

The Use of Aquatic Macrophyte Ecotoxicological Assays in Monitoring Coastal Effluent Discharges in Southern Australia

International Nuclear Information System (INIS)

Burridge, T.R.; Karistianos, M.; Bidwell, J.

1999-01-01

Germination inhibition of zoospores of the aquatic, brown algal macrophyte Ecklonia radiata was employed to assess the toxicity of sewage effluents under short to long term exposure and under modified salinity conditions. The rate of germination inhibition was determined for exposure times between 2 and 48 h in salinity modified and unmodified regimes and under reduced salinity conditions alone. The results indicated that rate of germination inhibition increased with duration of exposure to sewage effluents and to salinity reduction alone, and that response to the effluents may be enhanced under conditions of reduced salinity. Whilst the effect of primary treated effluent was primarily that of toxicity, secondary treated effluent effects appeared to be primarily that of reduced salinity although at a greater rate than would be expected for salinity reduction alone. The assay is suggested to provide a mechanism for monitoring sewage effluent quality and to monitor potential impacts of sewage effluent discharge on kelp communities in southern Australia

CY-1981 effluent monitoring report

International Nuclear Information System (INIS)

Honkus, R.J.

1982-05-01

The effluent monitoring programs at ICPP for calendar year 1981 are summarized. During the year, five significant occurrences or unplanned releases occurred. These are briefly described and tabulated. In none of the instances were the applicable Radiation Concentration Guides (RCG's) exceeded. A graphic summary of the total airborne, liquid and solid releases during CY-1981 is presented. Liquid waste activity was higher than anticipated due to various processing factors throughout the year. Solid waste jumped dramatically in December due to shipment of end-prices from the EBR-II fuel which was processed during the Electrolytic campaign

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

2003-12-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2002. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Z. K.; Oh, S. H. [Jeju National Univ., Jeju (Korea, Republic of)

1998-01-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 1997. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

2002-12-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2001. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

Decree No 74-1181 of 31 December 1974 concerning liquid radioactive effluent releases from nuclear installations

International Nuclear Information System (INIS)

1975-01-01

This Decree prescribes the licensing procedure for the release of liquid wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

Knolls Atomic Power Laboratory Environmental Monitoring Report, Calendar Year 2003

Energy Technology Data Exchange (ETDEWEB)

None

2003-12-31

The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations.

Knolls Atomic Power Laboratory Environmental Monitoring Report. Calendar Year 2003

International Nuclear Information System (INIS)

2003-01-01

The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations

Evaluation 2000 and regulation and method. Release monitoring and environmental surveillance around Cea centers

International Nuclear Information System (INIS)

2001-06-01

This publication counts for the year 2000 for the evaluation of liquid and gaseous radioactive effluents releases and the radioactivity levels measured in the vicinity of Cea centers, through the air, water, vegetation and milk surveillance. An analysis of the results from 1996 to 2000 allows to follow their evolution. A second booklet develops the sampling and measurement methods made on effluents in environment. It present besides the regulation applied to effluents monitoring. (N.C.)

Recommended parameters for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities

International Nuclear Information System (INIS)

Li Hong; Fang Dong; Sun Chengzhi; Xiao Naihong

2003-01-01

A set of models and default parameters are recommended for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities in order to standardize the environmental effect assessment of nuclear facilities, and to simplify the observation and investigation in early phase. The paper introduces the input data and default parameters used in the model

Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

International Nuclear Information System (INIS)

Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

1993-01-01

A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

Developments in radioactive scrap monitoring

International Nuclear Information System (INIS)

Bellian, J.G.

1997-01-01

Over the past ten years there have been major developments in radiation monitoring systems used for detecting shielded radioactive sources in scrap metal. The extent of the problem and industry's awareness of the problem have both grown significantly during that time. The multimillion dollar expenses associated with decontamination after a source passes into the melt and the potential health hazard to employees and the public have added further impetus to the development of monitoring systems. Early attempts at scrap monitoring could detect some radiation, but testing with real life situations showed them to be virtually incapable of detecting shielded sources of radioactivity in incoming vehicles. More sophisticated detector technology and the development of advanced software made useful by more powerful microprocessors led to successive generations of monitoring systems with order-of-magnitude improvement in detection capability. The next generation includes larger detectors and more complex algorithms offering further improvement in truck and rail car monitoring. Complete solutions require monitoring at additional locations within the site, such as the charge bucket and conveyor lines, and at the scrap processor's site

Radiation monitoring system in medical facilities

International Nuclear Information System (INIS)

Matsuno, Kiyoshi

1981-01-01

(1) RI selective liquid effluent monitor is, in many cases, used at medical facilities to obtain data for density of radioactivity of six radionuclides. In comparison with the conventional gross measuring systems, over-evaluation is less, and the monitor is more practical. (2) Preventive monitor for loss of radium needle is a system which prevents missing of radium needle at a flush-toilet in radium treatment wards, and this monitor is capable of sensing a drop-off of radium needle of 0.5 mCi (minimum). (3) Short-lived positron gas measuring device belongs to a BABY CYCLOTRON installed in a hospital, and this device is used to measure density of radioactivity, radioactive impurity and chemical impurity of produced radioactive gas. (author)

Design of position monitor module in radioactive material transport monitoring system

International Nuclear Information System (INIS)

Adi Abimanyu; Dwi Yuliansari N

2013-01-01

Aspects of safety and security of radioactive substances from the sender to the receiver is to be secured so as not to harm humans. In general, monitoring is done through conversation by telephone to determine the location and rate of exposure of radioactive substances. Through the development of science and technology makes it possible to develop a system of monitoring the transport of radioactive substances in real time by combining radiation monitor module, position monitors module and sending information nir-cable. Position monitor module developed using GPS-receiver and a micro controller ATMega8 based serial interrupts communication. Testing is done by testing communication between micro controller and GPS and also testing reading position by GPS receiver. From the test results concluded that the developed modules is good in serial communication is based on serial interrupts, good position measurement to be used outdoors and is not good enough for measurements indoors because the GPS receiver used is not using an outdoor antenna. (author)

Introducing radioactivity monitoring systems in the production of steel

International Nuclear Information System (INIS)

Sofilic, T.; Marjanovic, T.; Rastovcan-Mioc, A.

2005-01-01

Over the last twenty years, a significant number of cases of radioactive pollution has been recorded in metallurgical processes. However, it is not certain whether the pollution was caused by increased uncontrolled disposal of waste containing radionuclides or whether it was the result of increased radioactivity monitoring and control of metallic scrap. Many metal producers in the world have therefore implemented systematic monitoring of radioactivity in their production processes. Special attention was given to monitoring radioactivity in steel making processes, which is still the most applied construction material with an annual output of over billion tonnes all over the world. Drawing on the experience of the best known steel producers in Europe and world, Croatian steel mills find it necessary and justified to introduce radioactivity monitoring and control systems of radioactive elements in steel scrap, semi-finished and finished products. The aim of this paper is to point out the need to introduce the radioactivity monitoring and control in steel and steel-casting production, and to inform experts in Croatian steel mills and foundries about potential solutions and current systems. At the same time, we wanted to demonstrate how implementation of monitoring equipment can improve quality management and environmental management systems. This would render Croatian products competitive on the European market both in terms of physical and chemical properties and in terms of product quality certificates and radioactivity information. Since we lack our own standards and regulations to control both domestic and imported steel scrap, semi-finished products (crude steel, hot and cold rolled strip) and finished products, we need apply current international recommendations and guidelines, until we design our own monitoring system and adopt relevant legislation on the national level. This paper describes basic types of radioactivity monitoring and control systems, the most

Radioactivity Monitoring of the Irish Environment 2006

International Nuclear Information System (INIS)

Smith, V.; Dowdall, A; Fegan, M.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; Somerville, S.; Wong, J.; Pollard, D.

2007-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2006. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England, which are licensed by the UK Environment Agency, continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2006 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at ten stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows concentrations of caesium-137 to be measured; another is equipped to detect the presence of the gas krypton-85. This gas is released into the environment primarily as a result of the

Gaseous effluent monitoring and identification using an imaging Fourier transform spectrometer

Energy Technology Data Exchange (ETDEWEB)

Carter, M.R.; Bennett, C.L.; Fields, D.J.; Hernandez, J.

1993-10-01

We are developing an imaging Fourier transform spectrometer for chemical effluent monitoring. The system consists of a 2-D infrared imaging array in the focal plane of a Michelson interferometer. Individual images are coordinated with the positioning of a moving mirror in the Michelson interferometer. A three dimensional data cube with two spatial dimensions and one interferogram dimension is then Fourier transformed to produce a hyperspectral data cube with one spectral dimension and two spatial dimensions. The spectral range of the instrument is determined by the choice of optical components and the spectral range of the focal plane array. Measurements in the near UV, visible, near IR, and mid-IR ranges are possible with the existing instrument. Gaseous effluent monitoring and identification measurements will be primarily in the ``fingerprint`` region of the spectrum, ({lambda} = 8 to 12 {mu}m). Initial measurements of effluent using this imaging interferometer in the mid-IR will be presented.

The Radioactive Waste Management at Studsvik

Energy Technology Data Exchange (ETDEWEB)

Hedlund, R; Lindskog, A

1966-04-15

The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries.

The Radioactive Waste Management at Studsvik

International Nuclear Information System (INIS)

Hedlund, R.; Lindskog, A.

1966-04-01

The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries

Atomic Energy of Canada Limited monitoring tritiated water in air and water effluents

International Nuclear Information System (INIS)

Osborne, R.V.; Tepley, N.W

1978-01-01

Current on-line methods of monitoring effluents for tritium (as tritiated water, HTO) measure concentrations in air above 250 nCi/m 3 (approx. 10 kBq/m 3 ) and in water above 1 uCi/kg (approx. 40 kBq/kg). Some of the problems encountered in such monitoring are the presence of fission and activation products in the effluents and, particularly in water monitoring, the often dirty quality of the sample. In a new design of monitor, HTO is collected directly from air by a flow of liquid scintillator (LS). For water monitoring a flow of air continuously samples the water and transports HTO to the LS. The key features of the new design are that the high detection efficiency of LS is realizable, that the rate of use of LS is only approx. 2 mm 3 /s, that the controlled evaporation and metering of air provides the low flow of HTO needed for mixing with LS, and that accurate metering of a dirty effluent is not needed. The sensitivities for detecing tritium on-line are improved by at least an order of magnitude

AIR RADIOACTIVITY MONITOR

Science.gov (United States)

Bradshaw, R.L.; Thomas, J.W.

1961-04-11

The monitor is designed to minimize undesirable background buildup. It consists of an elongated column containing peripheral electrodes in a central portion of the column, and conduits directing an axial flow of radioactively contaminated air through the center of the column and pure air through the annular portion of the column about the electrodes. (AEC)

Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

Energy Technology Data Exchange (ETDEWEB)

Wormser, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

International Nuclear Information System (INIS)

1996-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

Development of radioactive surface contamination monitor

International Nuclear Information System (INIS)

Hashimoto, Tadao; Hasegawa, Toru; Fukumoto, Keisuke; Ooki, Yasushi

2008-01-01

In the radiation facilities such as nuclear power plants, surface contamination of the people accessing or articles conveyed in and out of the radiation controlled areas is detected and monitored by installing contamination monitors at the boundary of controlled areas and uncontrolled areas against the expansion of the radioactive materials to out of the facilities. It is required for the surface contamination of articles to be tightened of control criteria as 'Guidelines for discrimination ways of nonradioactive waste (not classified as radioactive waste) generated from nuclear power plants' (hereinafter referred to as 'the Guideline') was established by the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry in August, 2005. It predicts that the control criteria of monitors other than article monitors are also tightened in the future. Fuji electric has been fabricating and delivering surface contamination detecting monitors. Now we are developing the new contamination monitor corresponding to the tightening of the control criteria. 'Large article transfer monitor', 'Clothing monitor' and 'Body surface contamination monitor' are introduced in this article. (author)

Radioactivity Monitoring of the Irish Environment 2009

International Nuclear Information System (INIS)

McGinnity, P.; Currivan, L.; Dowdall, A.; Fegan, M.; Hanley, O.; Kelleher, K.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

2010-12-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2009. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2009 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

Radioactivity Monitoring of the Irish Environment 2008

International Nuclear Information System (INIS)

Fegan, M.; Currivan, L.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

2010-01-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2008. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2008 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

Radioactivity measurement of the liquid effluents of two university hospital methodology, problems arising

International Nuclear Information System (INIS)

Basse-Cathalinat, B.; Barthe, N.; Chatti, K.; Ducassou, D.

2005-01-01

The authors present methodology used to measure the radioactivity of the effluents at the output of two services of Nuclear medicine located in two Hospital complexes of the Area of Bordeaux. These measures are intended to answer at the requests of circular DGS/DHOS no 2001/323 of the Ministry for Employment and Solidarity. The selected method is more powerful since it is based on the use of a whole of spectrometry to very low background noise. These devices of measurements make it possible to take into account all the isotopes coming from a service of Nuclear medicine. The authors are conscious that of such measurements cannot be considered in all the services of Nuclear medicine. Other technical articles will specify simpler methods allowing a satisfactory management of the radioactive wastes. (author)

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed

The regulation of radioactive effluent release in France (mainly from large nuclear installations)

International Nuclear Information System (INIS)

Hebert, Jean.

1978-01-01

In parallel with the licensing system for construction and operation of classified or so-called large nuclear installations (INB) there are in France regulations for the release of radioactive effuents from such installations. The regulations applicable to installations other than INBs are not specifically of a nuclear nature, while those covering INBs, which are analysed in this study, in particular, cover effluent release in liquid or gaseous form. The licensing and control procedures for such release are analysed in detail. (NEA) [fr

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik.; Noh, Hyung Ah [Taejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2000-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 2000. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Sik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2001-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2002-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2003-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, J. S.; Kim, K. S.

1998-01-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 1998. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, Jae Sik; Noh, Hyung Ah

2001-12-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Order of 4 august 1989 on licensing the release of gaseous radioactive effluents by the Cattenom nuclear production centre (units 3 and 4)

International Nuclear Information System (INIS)

1989-08-01

This Order fixes the conditions and limits of authorised releases of gaseous radioactive effluents from Units 3 and 4 of the Cattenom nuclear power plant. It specifies these are maximum limits, below which the radioactive releases should be as low as possible [fr

Radioactive discharges and monitoring of the environment 1988

International Nuclear Information System (INIS)

1989-01-01

This annual report on Radioactive Discharges and Monitoring the Environment, 1988, summarises the programmes of Sellafield, Drigg, Chapelcross, Springfields and Capenhurst for monitoring the discharges of radioactive materials to the sea and the environment. Critical groups and environmental exposure pathways are identified and collective doses to these groups estimated. The disposal of radioactive wastes at each site is discussed. Certificates of authorisation are presented. A summary of recommended doses of specific radionuclides is given. (Author)

Radioactive source monitoring system based on RFID and GPRS

International Nuclear Information System (INIS)

He Haiyang; Zhou Hongliang; Zhang Hongjian; Zhang Sheng; Zhou Junru; Weng Guojie

2011-01-01

Nuclear radiation produced by radioactive source is harmful to the health of human body, and the lost and theft of radioactive source will cause environmental pollution and social panic. In order to solve the abnormal leaks, accidental loss, theft and other problems of the radioactive source, a radioactive source monitoring system based on RFID, GPS, GPRS and GSM technology is put forward. Radiation dose detector and GPS wireless location module are used to obtain the information of radiation dose and location respectively, RFID reader reads the status of a tag fixed on the bottom of the radioactive source. All information is transmitted to the remote monitoring center via GPRS wireless transmission. There will be an audible and visual alarm when radiation dose is out of limits or the state of radioactive source is abnormal, and the monitoring center will send alarming text messages to the managers through GSM Modem at the same time. Thus, the functions of monitoring and alarming are achieved. The system has already been put into operation and is being kept in functional order. It can provide stable statistics as well as accurate alarm, improving the supervision of radioactive source effectively. (authors)

1994 Environmental monitoring drinking water and nonradiological effluent programs annual report

International Nuclear Information System (INIS)

Andersen, B.D.; Brock, T.A.; Meachum, T.R.

1995-10-01

EG ampersand G Idaho, Inc., initiated monitoring programs for drinking water in 1988 and for nonradiological parameters and pollutants in liquid effluents in 1985. These programs were initiated for the facilities operated by EG ampersand G Idaho for the US Department of Energy at the Idaho National Engineering Laboratory. On October 1, 1994, Lockheed Idaho Technologies Company (LITCO) replaced EG ampersand G Idaho as the prime contractor at the INEL and assumed responsibility for these programs. Section I discusses the general site characteristics, the analytical laboratories, and sampling methodology general to both programs. Section 2, the Drinking Water Program, tracks the bacteriological, chemical, and radiological parameters required by State and Federal regulations. This section describes the drinking water monitoring activities conducted at 17 LITCO-operated production wells and 11 distribution systems. It also contains all of the drinking water parameters detected and the regulatory limits exceeded during calendar year 1994. In addition, groundwater quality is discussed as it relates to contaminants identified at the wellhead for LITCO production wells. Section 3 discusses the nonradiological liquid effluent monitoring results for 27 liquid effluent streams. These streams are presented with emphasis on calendar year 1994 activities. All parameter measurements and concentrations were below the Resource Conservation and Recovery Act toxic characteristics limits

Radioactivity Monitoring of the Irish Environment 2007

International Nuclear Information System (INIS)

Fegan, M.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; Smith, V.; Somerville, S.; Wong, J.; Pollard, D.

2008-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2007. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the envorinment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. In additiopn, some natural radioactivity exposure pathways are included in the programme including radioactivity in surface and ground drinking water. Radioactivity is present in the environment due to natural oprocesses, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in the Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2007 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at twelve stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows background concentrations of caesium-137 to be measured; another is equipped to

Partial monitoring system Radioactivity of the Environment, 2006

International Nuclear Information System (INIS)

Melicherova, T.

2007-01-01

In this report the Partial monitoring system 'Radioactivity of the Environment' for the year 2006 is presented. International co-operation of the Slovak Hydrometeorological Institute in the Partial monitoring system 'Radioactivity of the Environment' of the Slovak Republic, international co-operation as well as financial data are reviewed

Monitoring device for radioactive leakage from steam system in nuclear power plant

International Nuclear Information System (INIS)

Ogawa, Tateo; Sato, Kohei

1988-01-01

Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

Environmental monitoring report, Sandia Laboratories 1975

International Nuclear Information System (INIS)

Holley, W.L.; Simmons, T.N.

1976-04-01

Water and vegetation are monitored to determine Sandia Laboratories impact on the surrounding environment. Nonradioactive pollutants released are reported. Radioactive effluents are also reported and their person-rem contribution to the population is calculated

Releases of radioactivity at the Savannah River Plant, 1954--1985

International Nuclear Information System (INIS)

Zeigler, C.C.; Lawrimore, I.B.

1988-07-01

Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

Coir pith of the green coconut in the decontamination of radioactive aqueous effluent

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Raquel Almeida; Yamaura, Mitiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: quequelll_monteiro@yahoo.com.br; myamaura@ipen.br

2007-07-01

Industrial segments as plant of mining, hospitals and university generate considerable volumes of radioactive wastewater containing uranium. The increasing development of the use of the nuclear energy to lead away to an expansion of the sectors of the nuclear fuel cycle, but it leads to security problems and it appears the necessity of control of the removing of uranium and radioactive effluent treatments. Researches evaluate if the technique of the biosorption would promote an alternative process with attractive characteristics of cost-benefit. The residual biomass from agricultural activities has been studied and used as adsorbent of metals and organic composts by low cost, abundance and for being biodegradable. In this work, it is presented the efficiency of the coir pith for the adsorption of ions UO{sub 2}{sup 2+}. The coir pith is a by-product of the harvest of the coconut, a renewable natural source. The study was accomplished using the batch techniques. The influence from pH 2 to 5, the dose of the coir pith, equilibrium time and the models of kinetic reaction were investigated. It was verified that the adsorption increased with the increase of pH and of the dose. The equilibrium time was of 30 min and the best correspondence with the model of pseudo second-order was observed. The results obtained has been promising, so use as adsorbent of metallic ions represents an economic alternative in relation to the conventional treatment of effluent. (author)

Coir pith of the green coconut in the decontamination of radioactive aqueous effluent

International Nuclear Information System (INIS)

Monteiro, Raquel Almeida; Yamaura, Mitiko

2007-01-01

Industrial segments as plant of mining, hospitals and university generate considerable volumes of radioactive wastewater containing uranium. The increasing development of the use of the nuclear energy to lead away to an expansion of the sectors of the nuclear fuel cycle, but it leads to security problems and it appears the necessity of control of the removing of uranium and radioactive effluent treatments. Researches evaluate if the technique of the biosorption would promote an alternative process with attractive characteristics of cost-benefit. The residual biomass from agricultural activities has been studied and used as adsorbent of metals and organic composts by low cost, abundance and for being biodegradable. In this work, it is presented the efficiency of the coir pith for the adsorption of ions UO 2 2+ . The coir pith is a by-product of the harvest of the coconut, a renewable natural source. The study was accomplished using the batch techniques. The influence from pH 2 to 5, the dose of the coir pith, equilibrium time and the models of kinetic reaction were investigated. It was verified that the adsorption increased with the increase of pH and of the dose. The equilibrium time was of 30 min and the best correspondence with the model of pseudo second-order was observed. The results obtained has been promising, so use as adsorbent of metallic ions represents an economic alternative in relation to the conventional treatment of effluent. (author)

Environmental radioactivity monitoring in Republic of Serbia

International Nuclear Information System (INIS)

Joksic, J.; Radenkovic, M.; Tanaskovic, I.; Vujovic, M.; Vuletic

2011-01-01

According to environmental radioactivity monitoring programme continuous measurements of radioactivity in different samples are performed. Measurements are performed in aerosol samples, fallout, soil, surface waters, drinking water, food of animal and plant origin, milk and feeding stuffs. [sr

Survey monitoring of environmental radioactivity in Daegu area

Energy Technology Data Exchange (ETDEWEB)

Kang, H. D.; Lee, S. Y. [Kyungpook National Univ., Daegu (Korea, Republic of)

1998-01-15

The objectives of the project are to monitor an abnormal radiation level in Taegu and Kyungpook region, and to enhance our ability to prepare for the radiological emergency situation by establishing the radioactivity monitoring system in Taegu and Kyungpook region. Gross beta activities were measured and gamma radionuclides were analysed for the environmental samples of air-borned dust. precipitation. fallout and drinking water collected in Taegu radioactivity monitoring center. and gamma exposure rates were also measured. To establish the basic data base on the environmental radioactivity, gamma radionuclide analyses were carried out for the samples of soil, drinking water, grain, vegetable, milk, and fish which were obtained from 31 different areas, and the spatial gamma exposure rates from 61 different points were also measured in Taegu and Kyungpook region. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region.

Results of the F/H Effluent Treatment Facility biological monitoring program, July 1987--July 1991

International Nuclear Information System (INIS)

Specht, W.L.

1992-07-01

As required by the South Carolina Department of Health and Environmental Control (SCDHEC) under NPDES Permit SCO000175, biological monitoring was conducted in Upper Three Runs Creek to determine if discharges from the F/H Effluent Treatment Facility have adversely impacted the biotic community of the receiving stream. Data included in this summary report encompass July 1987 through July 1991. As originally designed, the F/H ETF was not expected to remove all of the mercury from the wastewater; therefore, SCDHEC specified that studies be conducted to determine if mercury was bioaccumulating in aquatic biota. Subsequent to approval of the biological monitoring program, an ion exchange column was added to the F/H ETF specifically to remove mercury, which eliminated mercury from the F/H ETF effluent. The results of the biological monitoring program indicate that at the present rate of discharge, the F/H ETF effluent has not adversely affected the receiving stream with respect to any of the parameters that were measured. The effluent is not toxic at the in-stream waste concentration and there is no evidence of mercury bioaccumulation

Radioactive standards and calibration methods for contamination monitoring instruments

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-06-01

Contamination monitoring in the facilities for handling unsealed radioactive materials is one of the most important procedures for radiation protection as well as radiation dose monitoring. For implementation of the proper contamination monitoring, radiation measuring instruments should not only be suitable to the purpose of monitoring, but also be well calibrated for the objective qualities of measurement. In the calibration of contamination monitoring instruments, quality reference activities need to be used. They are supplied in different such as extended sources, radioactive solutions or radioactive gases. These reference activities must be traceable to the national standards or equivalent standards. On the other hand, the appropriate calibration methods must be applied for each type of contamination monitoring instruments. In this paper, the concepts of calibration for contamination monitoring instruments, reference sources, determination methods of reference quantities and practical calibration methods of contamination monitoring instruments, including the procedures carried out in Japan Atomic Energy Research Institute and some relevant experimental data. (G.K.)

Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

International Nuclear Information System (INIS)

Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

1998-06-01

Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF

Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

1998-06-01

Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

Filtration device for active effluents

International Nuclear Information System (INIS)

Guerin, M.; Meunier, G.

1994-01-01

Among the various techniques relating to solid/liquid separations, filtration is currently utilized for treating radioactive effluents. After testing different equipments on various simulated effluents, the Valduc Center has decided to substitute a monoplate filter for a rotative diatomite precoated filter

Monitoring of radioactivity in the marine environment

International Nuclear Information System (INIS)

Bologa, A.S.

1992-01-01

The necessity of radioactivity monitoring in the marine environment was imposed by the increasing development of nuclear power and its world-wide use in many different segments of economic and social life. Both natural and artificial radioactivity play an important role in marine ecology and human health. In this respect three major facts continue to prevail in Romania. The fallout, the presence of the Danube river and the expectations for future energy production. Spatial and temporal monitoring of marine radioactivity along the Romanian Black Sea shore has been systematically performed in the Romanian Marine Research Institute in close co-operation with the Institute of Meteorology and Hydrology since 1981. Marine emerged and submerged sediments, coastal and offshore sea water, macroalgae, in vertebrates and fish off the Danube mouths and/or along the coast are monitored for natural and artificial radioactivity by means of beta gross measurements and gamma spectrometry. Concentrations of radionuclides as K-40, Cs-134, Cs-137 in abiotic and biotic samples, environmental distributions coefficients and concentrations factors (CF), as well as experimentally-derived CFs in marine biota as radioecological bioindicators are assessed and stored for a national data base. (author) 3 tabs., 18 refs

Sampling method of environmental radioactivity monitoring

International Nuclear Information System (INIS)

1984-01-01

This manual provides sampling methods of environmental samples of airborne dust, precipitated dust, precipitated water (rain or snow), fresh water, soil, river sediment or lake sediment, discharged water from a nuclear facility, grains, tea, milk, pasture grass, limnetic organisms, daily diet, index organisms, sea water, marine sediment, marine organisms, and that for tritium and radioiodine determination for radiation monitoring from radioactive fallout or radioactivity release by nuclear facilities. This manual aims at the presentation of standard sampling procedures for environmental radioactivity monitoring regardless of monitoring objectives, and shows preservation method of environmental samples acquired at the samplingpoint for radiation counting for those except human body. Sampling techniques adopted in this manual is decided by the criteria that they are suitable for routine monitoring and any special skillfulness is not necessary. Based on the above-mentioned principle, this manual presents outline and aims of sampling, sampling position or object, sampling quantity, apparatus, equipment or vessel for sampling, sampling location, sampling procedures, pretreatment and preparation procedures of a sample for radiation counting, necessary recording items for sampling and sample transportation procedures. Special attention is described in the chapter of tritium and radioiodine because these radionuclides might be lost by the above-mentioned sample preservation method for radiation counting of less volatile radionuclides than tritium or radioiodine. (Takagi, S.)

Radioactive effluent sources and special system of channels on the RA Reactor at the Boris Kidric Institute; Izvori radioaktivnih efluenata i specijalna kanalizacija u reaktoru RA Instituta Boris Kidric

Energy Technology Data Exchange (ETDEWEB)

Bojovic, P; Gacinovic, O; Milosevic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

1964-10-15

The paper describes the place of origin, composition and activity of radioactive effluents appearing in some reactor systems and special channels for carrying these effluents to disposal basins located outside the reactor building (author)

HMIP Monitoring Programme radioactive substances report for 1990

International Nuclear Information System (INIS)

1992-03-01

The programme of environmental monitoring of radioactive substances in England and Wales during 1990, was completed satisfactorily under the auspices of Her Majesty's Inspectorate of Pollution. The programme concentrates on monitoring activity levels in environmental materials which might result in radiation exposure of the public from non-food pathways. The programme acts as a check on site operator's returns and provides independent data on the environmental impact of authorised disposals of radioactive wastes and on radiation doses to critical groups of the public. This report presents the data from this continuing monitoring programme. The monitoring was carried out at installations controlled by British Nuclear Fuels PLC, Nuclear Electric the United Kingdom Atomic Energy Authority, Amersham International PLC, the Ministry of Defence, at two non-nuclear sites which use tritium, the works of Capper Pass Ltd who carry out lead smelting and at several landfill sites where controlled buried of low-level radioactive wastes is carried out. (Author)

Environmental and effluent monitoring at ANSTO sites, 2004-2005

International Nuclear Information System (INIS)

Hoffmann, Emmy L.; Loosz, Tom; Ferris, John M.; Harrison, Jennifer J.

2005-01-01

This report presents the results of ANSTO's environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) sites, from July 2004 to June 2005. Effective doses to the critical group of members of the public potentially affected by routine airborne emissions from the LHSTC were less than 0.005 mSv/year. This estimated maximum potential dose is less than 24% of the ANSTO ALARA objective of 0.02 mSv/year, and much lower than the public dose limit of 1 mSv/year that is recommended by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The effective doses to the critical group of members of the public potentially exposed to routine liquid effluent releases from the LHSTC have been realistically estimated as a quarter (or less) of the estimated doses to the critical group for airborne releases. The levels of tritium detected in groundwater and stormwater at the LHSTC were less than those set out in the Australian Drinking Water Guidelines. The airborne and liquid effluent emissions from the NMC were below both the ARPANSA-approved notification levels and Sydney Water limits for acceptance of trade wastewater to sewer. Results of environmental monitoring at both ANSTO sites confirm that the facilities continue to be operated well within regulatory limits. ANSTO's routine operations at the LHSTC and NMC make only a very small addition to the natural background radiation dose of ∼1.5 mSv/year experienced by members of the Australian public

Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche

International Nuclear Information System (INIS)

2003-01-01

This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

Design of automatic control and measurement software for radioactive aerosol continuity monitor

International Nuclear Information System (INIS)

Mao Yong; Li Aiwu

1997-01-01

The radioactive aerosol continuity measurement is very important for the development of nuclear industry, and it is the major method to measure and find out the leakage of radioactive material. Radioactive aerosol continuity monitor is the advanced method for the radioactive aerosol continuity measurement. With the development of nuclear industry and nuclear power station, it is necessary to design and automatic continuity measurement device. Because of this reason, the authors developed the first unit of radioactive aerosol continuity monitor and adopted the ministry appraisal. The design idea and method of automatic control and measurement for radioactive aerosol continuity monitor are discussed

Survey monitoring of environmental radioactivity in Daegu area

International Nuclear Information System (INIS)

Kang, Hee Dong; Lee, Hae Young; Yang, Chan Sun

2001-12-01

The objectives of the project are to monitor an abnormal radiation level in Taegu and Kyungpook region, and to enhance our ability to prepare for the radiological emergency situation by establishing the radioactivity monitoring system in Taegu and Kyungpook region. In this report, we summarized a gamma exposure rates, a gross beta and gamma radionuclide activities for the environmental samples of airborned-dust. precipitation, fallout and tap water collected in Taegu radioactivity monitoring center, and a gamma radionuclide activities for the 28 grocery samples, such as tea, nut and mushroom, rice, chinese cabbage, wormwood and pine needles, soil and drinking water which were obtained from Taegu and Kyungpook region to establish the basic data base for estimating the internal exposure. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region

Environmental monitoring at the Lawrence Livermore National Laboratory. 1982 annual report

International Nuclear Information System (INIS)

Griggs, K.S.; Gonzalez, M.A.; Buddemeier, R.W.

1983-01-01

Environmental monitoring efforts spanned air, water, vegetation and foodstuffs, and radiation doses. Monitoring data collection, analysis, and evaluation are presented for air, soils, sewage, water, vegetation and foodstuffs, milk, and general environmental radioactivity. Non-radioactive monitoring addresses beryllium, chemical effluents in sewage, noise pollution, and storm runoff and liquid discharge site pollutants. Quality assurance efforts are addressed. Five appendices present tabulated data; environmental activity concentration; dose calculation method; discharge limits to sanitary sewer systems of Livermore; and sampling and analytical procedures for environmental monitoring

Radioactivity Monitoring of the Irish Environment 2003-2005

International Nuclear Information System (INIS)

Ryan, R.W.; Dowdall, A; Fegan, M.F.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; McKittrick, L.; McMahon, C.A.; Murray, M.; Smith, K.; Sequeira, S.; Wong, J.; Pollard, D.

2007-05-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) between 2003 and 2005. This programme aims to assess the exposure of the Irish population to anthropogenic radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl and the routine licensed discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the North-West of England continue to be the dominant source of anthropogenic radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII during the reporting period include; assessment of ambient radioactivity based on measurements of radioactivity in air and external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and miscellaneous ingredients; assessment of levels of radioactivity in the marine environment based on sampling and measurements of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at eleven stations located throughout the country. One station is equipped with a high volume sampler, which allows global fallout concentrations to be measured, and one is equipped to detect the presence of the gas krypton-85. Krypton-85 is released into the environment primarily as a result of the reprocessing of nuclear

Environmental monitoring of low-level radioactive materials

International Nuclear Information System (INIS)

Jester, W.A.; Yu, C.

1985-01-01

The authors discuss some of the current rationale behind the environmental monitoring of low-level radioactive materials are as follows: Committee 4 of the International commission on Radiological Protection (ICRP) defined three broad objectives for environmental monitoring: 1) assessment of the actual or potential exposure of humans to radioactive materials or radiation present in their environment or the estimation of the probable upper limits of such exposure; 2) scientific investigation, sometimes related to the assessment of exposures, sometimes to other objectives; 3) improved public relations. Various regulations have been written requiring environmental monitoring to ensure that the public is not being exposed to excessive amounts of radiation from natural sources or from human activities. An example of the monitoring of natural sources of radiation is a requirement of the Environmental Protection Agency's (EPA) National Interim Primary Drinking Water Regulations whereby U.S. water supply companies must have drinking water monitored at least once every four years for radionuclides, primarily the naturally occurring radium-226

Monitoring radioactivity in the environment: context, objectives, challenges and prospects

International Nuclear Information System (INIS)

Collet, J.; Jaunet, P.

2010-01-01

The aims of environmental radioactivity monitoring are multiples: protection of human health and environment, knowledge of the radiological status of the environment, early detection of radiological events, public information. This monitoring is ensured by several stakeholders (licensees, IRSN, ASN, state and local authorities, associations...) and in all environment compartments (air, water, soil, fauna and flora...). Within a European regulatory context, the Nuclear Transparency and Security Act 2006-686 of 13 June 2006 (TSN Act) reinforces the importance attached to consideration of safety, radiation protection and the environment. Other developments in the scope of environmental radioactivity must be noted: new stakeholders, lower background radiation, deployment of the French National Network of Environmental Radioactivity Monitoring (RNM), evolution of the ICPR thoughts to take better account of environmental protection, post-accident management doctrine, new concerns about environmental behaviour of some radionuclides. In order to maintain a quality policy in the field of environmental radioactivity measurements and to ensure the transparency of information, ASN will make sure that the strategy of environmental radioactivity monitoring will take into account these concerns. (author)

Environmental and Effluent Monitoring at ANSTO Sites, 2002-2003

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, E L; Ferris,; Markich, S J

2004-10-01

This report presents the results of environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) from January 2002 to June 2003. Potential effective dose rates to the general public from airborne discharges from the LHSTC site were less than 0.01 mSv/year, well below the 1 mSv/year dose rate limit for long term exposure that is recommended by the Australian National Occupational Health and Safety Commission. The effective dose rates to hypothetical individuals potentially exposed to radiation in routine liquid effluent discharges from the LHSTC were recently calculated to be less than 0.001 mSv/year. This is much less than dose rates estimated for members of public potentially exposed to airborne emissions. The levels of tritium detected in roundwater and stormwater at the LHSTC were less than the Australian drinking water guidelines. The airborne and liquid effluent emissions from the NMC were below the ARPANSA-approved notification levels and NSW EPA limits, respectively. ANSTO's routine operations at the LHSTC and the NMC make only a very small addition to the natural background radiation dose experienced by members of the Australian public. (authors)

Environmental monitoring for radioactivity in Scotland: 1981 to 1985

Energy Technology Data Exchange (ETDEWEB)

Anon.

1987-01-01

A bulletin, prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The monitoring results for discharges to both the atmosphere and the sea over the period 1981 to 1985 are presented for BNFL's Chapelcross and Sellafield Works, UKAEA Dounreay Nuclear Power Development Establishment, SSEB Hunterston Power Station and MOD Naval Installations. It is concluded that public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits.

Radioactivity monitor for high-performance liquid chromatography

International Nuclear Information System (INIS)

Reeve, D.R.; Crozier, A.

1977-01-01

The coupling of a homogeneous radioactivity monitor to a liquid chromatograph involves compromises between the sensitivity of the monitor and the resolution and speed of analysis of the chromatograph. The theoretical relationships between these parameters are considered and expressions derived which make it possible to calculate suitable monitor operating conditions for most types of high-performance liquid chromatography

Derived release limits (DRL's) for airborne and liquid effluents from the Chalk River Nuclear Laboratories during normal operations

International Nuclear Information System (INIS)

Palmer, J.F.

1981-02-01

Derived release limits (DRL's), based on regulatory dose limits, have been calculated for routine discharges of radioactivity in airborne and liquid effluents from the Chalk River Nuclear Laboratories. Three types of sources of airborne effluents were considered: the NRX/NRU stack, the 61 m stack connected to the 99 Mo production facility, and a roof vent typical of those installed on several buildings on the site. Sources of liquid effluents to the Ottawa River were treated as a single source from the site as a whole. Various exposure pathways to workers on the site and to members of the public outside the site boundary were considered in the calculations. The DRL's represent upper limits for routine emissions of radioactivity from the Chalk River Nuclear Laboratories to the surrounding environment. Actual releases are regulated by Administrative Levels, set lower than the DRL's, and are confirmed by monitoring. (author)

Survey of radioactive effluent releases from byproduct material facilities. Technical report

International Nuclear Information System (INIS)

Cook, J.R.

1981-08-01

A survey of over 3,000 NRC byproduct material licensees was conducted in late 1980 to collect data on annual effluent releases of radioactivity. The survey was conducted through a questionnaire, which was sent to NRC licensees who handle radioactive material in unsealed form, i.e., research, medical, and industrial institutions. Principal findings from the survey analysis are as follows: More than 98% of the reported annual releases to air (484 to 490) yield calculated average concentrations at the boundary of the unrestricted area that were at 1% or less than the maximum permissible concentration (MPC) of Appendix B, Table II, Column 1 of 10 CFR 20. The largest reported annual release was estimated to yield a concentration that was approximately 12% of MPC, the 5 other releases ranged from 1 to 10% of MPC. All reported annual releases of liquid waste were within the limits specified by NRC with most facilities reporting annual releases of only a fraction of a curie. Based on the data provided by licensees and analyzed in this report, it appears that in general the environmental impacts from research, medical and industrial institutions and organizations licensed by the NRC to possess and use byproduct materials are minimal and correspond to a small fraction of that from natural background

Monitoring programme. Radioactive substances report for 1994

International Nuclear Information System (INIS)

1995-09-01

In the United Kingdom, Her Majesty's Inspectorate of Pollution commissions independent monitoring of radioactive discharges to the environment. This report presents the results of such monitoring for 1994. It covers nuclear sites, two non-nuclear sites which use large amounts of tritium and several landfill sites which receive low-level radioactive waste for controlled burial. The monitoring programme concentrates on activity levels in environmental materials that might result in exposure of the public to radiation from non-food pathways. The results show that exposures from these pathways in 1994 remain similar to those in previous years and in all cases are estimated to have been substantially lower than the International Commission on Radiological Protection's recommended dose limit of 1mSv per year. (6 figures; 20 tables; 29 references) (UK)

Radioactivity monitoring status in French Polynesia in 2008. Results from IRSN's monitoring network

International Nuclear Information System (INIS)

2009-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. The task addresses two objectives: - To monitor the levels of artificial radioactivity in all sectors of the environment and in major foodstuffs; - To estimate the exposure of the Polynesian population to this artificial radioactivity. The IRSN has monitored radioactivity levels in French Polynesia, excluding the Mururoa and Fangataufa nuclear experimentation centres, since 1962. This task is realized by the IRSN's Environmental Study and Monitoring Laboratory located in Tahiti (Vairao) This monitoring was instigated at the time when atmospheric nuclear weapons testing was being performed by the major powers (the United States, the Soviet Union, the United Kingdom, France and China), causing fallout of artificial radionuclides, over several years, on a planetary scale. In French Polynesia, the IRSN is most particularly interested in fallout resulting from the 41 tests carried out by France in this region of the globe between 1966 and 1974, and in its consequent effects on the population. Today, just as in metropolitan France, the IRSN carries out monitoring as part of its mission to constantly monitor radiological protection factors. The monitoring takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes and consists of taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. For more than 40 years, the IRSN takes part in the evaluation of the dosimetric consequences of these atmospheric depositions in French Polynesia. This laboratory is established in Tahiti. The ingestion component of this dosimetric evaluation requires to collect the most representative samples of

Terrestrial radioactivity monitoring programme (TRAMP) report for 1986

International Nuclear Information System (INIS)

1988-01-01

The Ministry of Agriculture, Fisheries and Food (MAFF) undertakes a comprehensive independent monitoring programme for radioactivity in terrestrial foodstuffs in England and Wales, this report presents the results from the first full year of operation of this programme and complements the data published annually by the Ministry's Directorate of Fisheries Research in respect of the aquatic environment. This work is undertaken in Wales on behalf of the Secretary of State. The Terrestrial Radioactivity Monitoring Programme (TRAMP) concentrates on samples of agricultural produce (milk, crops, meat) collected from the vicinity of the major nuclear sites in England and Wales and is independent of monitoring undertaken for various purposes by site operators. (author)

Design, calculation and testing on mock-up of B(U) f type LR 56 packaging for radioactive liquid effluent transport

International Nuclear Information System (INIS)

Belaud; Leconnetable; Daspet; Tombini; Tanguy

1986-06-01

Transport of radioactive acid liquid effluents are effected on tank truck inside nuclear center of the CEA. The cylindrical packaging type B(U) f has a capacity of 4,000l, a maximum permissible activity of 110 T Bq (3x10 4 Ci) and comprises a central element for liquid effluent containment to prevent contamination of environment and peripheral elements for mechanical, biological and thermal protection. This packaging is fixed on a trailer associated with a control box. Design and equipment of the packaging are studied for a maximum safety and in accordance with regulations [fr

Synthesis of the IRSN report of the management of effluents in operating nuclear plants, and of associated radioactive and chemical rejections

International Nuclear Information System (INIS)

2009-05-01

This report discusses the various improvements proposed by the IRSN to EDF for a better management of effluents and rejections in nuclear plants. These improvements should bear on a better understanding of the production, of the behaviour and of the treatment of radioactive compounds and of associated chemical compounds. They should also bear on the design of the installations and their inspection, operation practices, the use of local good practices, the organisation, the control of rejections, the control of underground waters of nuclear sites, experience feedback, the documentation on effluents and rejections

Some analytical methods used by the Marcoule Centre for the control of radioactive effluents; Quelques methodes analytiques, utilisees sur le centre de Marcoule pour le controle radioactif des effluents

Energy Technology Data Exchange (ETDEWEB)

Scheidhauer, J.; Messainguiral, L.; Drogue, N.; Meiranesio, A. M.

1962-07-09

After three years of operation, the authors propose a review of the various methods used to determine the radioactivity of wastewaters released by the Marcoule Centre Laboratory. They describe the three main steps of this control: firstly, measurements of the global alpha radioactivity and beta radioactivity (principle and measurement method), secondly, dosing of strontium 89 and strontium 90 (principle, used reactants, operation mode for nitric compound precipitation, ferric decontamination, separation of barium 140, oxalic precipitation, precipitate counting, exploitation of counting results), and thirdly, the possible dosing of other fission products present in the effluents: cerium 144, plutonium (by two different methods), natural uranium, caesium 137, zirconium 95, niobium 95, ruthenium 103 and 106, iodine 131. The principle, reactants, operational mode with different precipitations, measurement devices are indicated for each of these radio-elements.

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

Energy Technology Data Exchange (ETDEWEB)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

2017-07-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

International Nuclear Information System (INIS)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

2017-01-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Liquid effluent retention facility final-status groundwater monitoring plan

International Nuclear Information System (INIS)

Sweeney, M.D.; Chou, C.J.; Bjornstad, B.N.

1997-09-01

The following sections describe the groundwater-monitoring program for the Liquid Effluent Retention Facility (LERF). The LERF is regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The LERF is included in the open-quotes Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, Permit WA890008967close quotes, (referred to herein as the Permit) (Ecology 1994) and is subject to final-status requirements for groundwater monitoring (WAC 173-303-645). This document describes a RCRA/WAC groundwater detection-monitoring program for groundwater in the uppermost aquifer system at the LERF. This plan describes the LERF monitoring network, constituent list, sampling schedule, statistical methods, and sampling and analysis protocols that will be employed for the LERF. This plan will be used to meet the groundwater monitoring requirements from the time the LERF becomes part of the Permit and through the post-closure care period, until certification of final closure

Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

International Nuclear Information System (INIS)

Hoffmann, E.L.; Camilleri, A.; Loosz, T.; Farrar, Y.

1995-12-01

Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs

Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, E L; Camilleri, A; Loosz, T; Farrar, Y

1995-12-01

Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs.

The effluent problem in a plutonium production centre

International Nuclear Information System (INIS)

Galley, R.; Cantel, J.

1960-01-01

The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [fr

Radioactive wastes management in a radiochemistry laboratory

International Nuclear Information System (INIS)

Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

2009-01-01

The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

Design and installation of a laboratory-scale system for radioactive waste treatment

International Nuclear Information System (INIS)

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

1980-05-01

Described are the mechanical design features and remote installation of a laboratory-scale radiochemical immobilization system which is to provide a means at Pacific Northwest Laboratory of studying effluents generated during solidification of high-level liquid radioactive waste. Detailed are the hot cell, instrumentation, two 4-in. and 12-in. service racks, the immobilization system modules - waste feed, spray calciner unit, and effluent - and a gamma emission monitor system for viewing calcine powder buildup in the spray calciner/in-can melter

Environmental monitoring at the Lawrence Livermore National Laboratory. 1984 annual report

International Nuclear Information System (INIS)

Griggs, K.S.; Myers, D.S.; Buddemeier, R.W.

1985-02-01

A strict effluent-control program that emphasizes controlling effluents at the source has been in effect since LLNL began operation. The Environmental Monitoring program evaluates the effectiveness of these measures, documents whether effluents from LLNL and Site 300 operations are within applicable standards, and estimates the impact of these operations on the environment. Sensitive monitoring equipment is used that can detect radioactive and nonradioactive pollutants at environmental background levels. The program includes the collection and analysis of air, soil, water, sewer effluent, vegetation, foodstuffs, and milk samples. Also, environmental background radiation is measured at numerous locations in the vicinity of LLNL using gamma and neutron dosimeters. This report summarizes the results of the 1984 program. 28 refs, 25 figs., 40 tabs

Ionization chamber for monitoring radioactive gas

International Nuclear Information System (INIS)

Kotrappa, P.; Dempsey, J.

1992-01-01

This present invention provides simple, effective and accurate cumulative measurement of radioactive gas over a time period. Measurements of radioactive gas are important for many purposes. Tritium concentrations in potentially exposed workers are measured, for example, with periodic urine specimens. Carbon-14 serves as a useful research tool for monitoring the progress of many chemical and biological reactions and interactions. For example, many microorganisms break down carbon-14 containing compounds in sugar to produce carbon-14 dioxide gas which can be collected and measured to determine various characteristics of the microorganisms. Both tritium and carbon-14 dioxide produce low energy radiation which cannot be easily measured by conventional radioactivity detectors. (author). 4 figs

Ionization chamber for monitoring radioactive gas

Energy Technology Data Exchange (ETDEWEB)

Kotrappa, P; Dempsey, J

1992-09-22

This present invention provides simple, effective and accurate cumulative measurement of radioactive gas over a time period. Measurements of radioactive gas are important for many purposes. Tritium concentrations in potentially exposed workers are measured, for example, with periodic urine specimens. Carbon-14 serves as a useful research tool for monitoring the progress of many chemical and biological reactions and interactions. For example, many microorganisms break down carbon-14 containing compounds in sugar to produce carbon-14 dioxide gas which can be collected and measured to determine various characteristics of the microorganisms. Both tritium and carbon-14 dioxide produce low energy radiation which cannot be easily measured by conventional radioactivity detectors. (author). 4 figs.

Environmental radioactivity monitoring in Greece

International Nuclear Information System (INIS)

Maltezos, A.; Potiriadis, C.; Aravantinos, A.

1997-01-01

Greek Atomic Energy Commission (GAEC) is the national organization responsible for the environmental radioactivity measurements in Greece. In order to monitor the radioactivity, 12 stations were placed all over Greece. Each station is equipped with NaI detector, measuring daily the total gamma dose rates. After the Chernobyl experience many countries have installed dense automatic networks, for measuring environmental radioactivity and serving as an early warning systems. In Greece a small telemetric network of two stations was installed in Athens area as a pilot project. Each station consists of two GM detectors (for low and high dose rate respectively). Data are collected for every ten minutes sampling time. Regration time of one hour is obtained. In case of level one and level two alarm states, the sampling time intervals are ten and one minutes respectively. The measurements are obtained by the above stations using the lines of the telephone network, and stored in the central station. Financial support to upgrade the existing telemetric system was assured by the addition of 25 new telemetric stations which will cover madly the northern part bordering to other states with nuclear power plants.In order to complete the network, we plan to add more stations to measure the gamma dose rates spread all over Greece, and also monitor river water. (authors)

A study on the diffusion of gaseous radioactive effluents based on the statistical method

International Nuclear Information System (INIS)

Na, Man Gyun; Lee, Goung Jin

1998-01-01

A diffusion model of radioactive gaseous effluents is improved to apply for domestic nuclear power plants. Up to now, XOQDOQ computer code package developed by U. S NRC has been used for the assessment of radioactive plume dispersion by normal operation of domestic nuclear power plants. XOQDOQ adopts the straight-line Gaussian plume model which was basically derived for the plane terrain. However, since there are so many mountains in Korea, the several shortcomings of XOQDOQ are improved to consider the complex terrain effects. In this work, wind direction change is considered by modifying the wind rose frequency using meteorological data of the local weather stations. In addition, an effective height correction model, a plume reduction model due to plume penetration into mountain, and a wet deposition model are adopted for more realistic assessments. The proposed methodology is implemented in Yonggwang nuclear power plants, and can be used for other domestic nuclear power plants

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

International Nuclear Information System (INIS)

2001-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

Energy Technology Data Exchange (ETDEWEB)

None

2001-12-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999.

On-line liquid-effluent monitoring of sewage at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Dreicer, M.; Cate, J.L.; Rueppel, D.W.; Huntzinger, C.J.; Gonzalez, M.A.

1982-01-01

An automatic on line sewage effluent monitoring system has been developed. A representative fraction of the total waste stream leaving the site is monitored for pH, radiation, and metals as it passes through a detection assembly. This assembly consists of an industrial pH probe, NaI radiation detectors, and an x-ray fluorescence metal detector. A microprocessor collects, reduces and analyzes the data to determine if the levels are acceptable by established environmental limits. Currently, if preset levels are exceeded, a sample of the suspect sewage is automatically collected for further analysis, and an alarm is sent to a station where personnel can be alerted to respond on a 24-hour basis. Since at least four hours pass before LLNL effluent reaches the treatment plant, sufficient time is available to alert emergency personnel, evaluate the situation, and if necessary arrange for diversion of the material to emergency holding basins at the treatment plant. Information on the current system is presented, and progress is reported in developing an on-line tritium monitor as an addition to the assembly

Monitoring dissolved radioactive cesium in Abukuma River in Fukushima Prefecture

International Nuclear Information System (INIS)

Yasutaka, Tetsuo; Kawabe, Yoshishige; Kurosawa, Akihiko; Komai, Takeshi

2013-01-01

Radioactive materials were released into the atmosphere and deposited over wide areas of farmland, forests, and cities; elevated levels of "1"3"1I, "1"3"4Cs, and "1"3"7Cs have been detected in these areas due to the accident at the Tokyo Power Fukushima Daiichi Nuclear Power Plant caused by the April 2011 earthquake and tsunami in eastern Japan. Radioactive Cs deposited on farmland and forests gradually leaches into water bodies such as mountain streams and rivers adsorbed onto particles or in a dissolved state. It is important to calrify the level of dissolved and total radioactive Cs in environmental water for forecasting the of discharge of radioactive Cs from forest and watersheds, assessing on the effect of dissolved and total radioactive Cs on not only irrigation water but also rice and other crops, and evaluating the transport of radioactive Cs from rivers to costal areas. Therefore, it is important to monitor their levels in Fukushima Prefecture over time. In this research, we monitored the levels of dissolved and total radioactive Cs in Abukuma River using a conventional evaporative concentration method. By monitoring the river waters since September 2012, it was estimated that the levels of dissolved radioactive Cs were less than 0.128 Bq/L and those of total radioactive Cs were less than 0.274 Bq/L in the main stream and branches of Abukuma River in the low suspended solid condition. (author)

Monitoring of covering model of the National radioactive waste repository

International Nuclear Information System (INIS)

Jezikova, M.

2009-01-01

The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

Management on radioactive wastes

International Nuclear Information System (INIS)

Balu, K.; Bhatia, S.C.

1979-01-01

The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

Analysis and study on generic models for use in assessing the impact of radioactive liquid effluent to the environment

International Nuclear Information System (INIS)

Ma Wenlin; Cao Jianzu; Fang Dong

2008-01-01

The assessment of the impact of discharges of radioactive substances into surface water under normal condition of nuclear facilities is an important part of the environmental impact analysis. Generic methods for assessing the impact of radioactive liquid effluent release into surface water provided by IAEA Safety Reports Series 19 are studied in this paper, and also an example calculation that assesses the impact of radioactive surface water discharge of HTR-PM ( High Temperature Air-cooled Reactor demonstration unit) in Anhui is presented in this paper to illustrate that a simplified but conservative assessment can be used for the purpose of screening proposed radioactive discharges. If the results meet the relevant requirements specified by the relevant regulatory authority, the further calculations are not needed. If they fails to meet the requirements, the more field data are to be sampled for calculations by more sophisticated mode or otherwise. (authors)

Chemical processing of liquid effluents in reprocessing plants: experience gained in France

International Nuclear Information System (INIS)

Fernandez, N.; Pottier, P.; Taillard, D.

1977-01-01

The radionuclides present in radioactive liquid effluents are precipitated for two purposes, viz: 1) to reduce the radioactivity to a level at which the liquids may be discharged; 2) to concentrate the radioactive compounds in the smallest possible volume for storage. The scientific principles of the radionuclide precipitation process are reviewed in the first part, which covers the solubility product, adsorption onto the surface of the precipitates, co-precipitation by isomorphism, ion-exchange on precipitates, etc. The paper goes on to discuss flocculation techniques, flocculation monitoring (zeta potential etc.) and methods of separating the solid and liquid phases. The specific methods for precipitating the main radionuclides are then described, with special reference to Sr, Cs, Ru, Co and Sb. The synergism of certain methods of precipitation is also discussed. The main part of the paper concerns the application of chemical processes for purifying low and medium active effluents in the Marcoule and La Hague centres. Particular emphasis is placed on the development of the processes used and the improvement of performance. Lastly, the paper discusses the possibilities offered in final treatment in such a way as to determine the limits to the effectiveness of the chemical processes. (orig.) [de

Comparison of monitoring technologies for CO2 storage and radioactive waste disposal

International Nuclear Information System (INIS)

Ryu, Jihun; Koh, Yongkwon; Choi, Jongwon; Lee, Jongyoul

2013-01-01

The monitoring techniques used in radioactive waste disposal have fundamentals of geology, hydrogeology, geochemistry etc, which could be applied to CO 2 sequestration. Large and diverse tools are available to monitoring methods for radioactive waste and CO 2 storage. They have fundamentals on geophysical and geochemical principles. Many techniques are well established while others are both novel and at an early stage of development. Reliable and cost-effective monitoring will be an important part of making geologic sequestration a safe, effective and acceptable method for radioactive waste disposal and CO 2 storage. In study, we discuss the monitoring techniques and the role of these techniques in providing insight in the risks of radioactive waste disposal and CO 2 sequestration

Treated Effluent Disposal Facility

Data.gov (United States)

Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

Analysis of adaptability of radioactive liquid effluent discharge under normal condition of inland nuclear power plant

International Nuclear Information System (INIS)

Xu Yueping; Zhang Bing; Chen Yang; Zhu Lingqing; Tao Yunliang; Shangguan Zhihong

2011-01-01

The discharge of radioactive liquid effluent from inland nuclear power plant under normal operation is an important part to be considered in environmental impact assessment. Requirements of newly revised and upcoming standards GB 6249 and GB 14587 are introduced in this paper. Through an example of an inland NPP siting in the preliminary feasibility study phase, the adaptability to the relevant regulations in the site selection is analyzed. Also, the concerned problems in the design of AP1000 units are addressed. (authors)

Radioactive effluents from nuclear power stations and reprocessing plants in the European Community

International Nuclear Information System (INIS)

1978-04-01

The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

Environmental monitoring of nuclear facilities

International Nuclear Information System (INIS)

Papadopoulos, D.; Winter, M.

1982-01-01

Environmental monitoring adds to the control of emissions of radioactive substances from nuclear facilities. The radioactive substances released with the exhaust air and the liquid effluent result in impact levels in the immediate vicinity, which must be ascertained by measurement. Impact control serves for the quantitative assessment of man-made radioactivity in different media of relevant pathways and for the direct assessment of the radiation exposure of the public living in the vicinity. In this way, the radiation exposure of the environment, which can be calculated if the emission data and the meteorological diffusion parameters are known, is controlled directly. (orig./RW)

Monitoring of radioactivity in 1979

International Nuclear Information System (INIS)

Data are given on the monitoring of radioactive contamination of air and some food stuffe at world locations throughout Western South America, South Pacific and Africa during 1979. Data are included on the total β and γ activity and radionuclide content in air, milk and other environmental samples ( 131 I, 90 Sr, 137 Cs) [fr

Monitoring quantity and quality of pangasius pond effluent : report of a monitoring program and recommendations for certification

NARCIS (Netherlands)

Heijden, van der P.G.M.; Poelman, M.; Vo Minh Son,; Duong Nhut Long,; Bosma, R.H.

2011-01-01

The quantity and quality of pangasius pond effluent was monitored by means of monthly sampling during a study conducted on four striped catfish farms located in the Mekong Delta, Vietnam. The study was undertaken to test the practical implications of the standards and guidelines with regard to

Flow proportional sampling of low level liquid effluent

International Nuclear Information System (INIS)

Colley, D.; Jenkins, R.

1989-01-01

A flow proportional sampler for use on low level radioactive liquid effluent has been developed for installation on all CEGB nuclear power stations. The sampler, operates by drawing effluent continuously from the main effluent pipeline, through a sampler loop and returning it to the pipeline. The effluent in this loop is sampled by taking small, frequent aliquots using a linear acting shuttle valve. The frequency of operation of this valve is controlled by a flowmeter installed in the effluent line; sampling rate being directly proportional to effluent flowrate. (author)

Storage of radioactive material - accidents - precipitation - personnel monitoring

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-12-01

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

Radioactivity monitoring of fallout, water and ground

International Nuclear Information System (INIS)

Radosavljevic, R.

1961-01-01

During 1961, the radioactivity monitoring of the Boris Kidric Institute site covered monitoring of the total β activity of the fallout and water on the site. Activity of the fallout was monitored by measuring the activity of the rain and collected sedimented dust form the atmosphere. Water monitored was the water from Danube and river Mlaka, technical and drinking water. Plants and soil activity were not measured although sample were taken and the total β activity will be measured and analysed later

Monitoring of radioactivity in 1973

International Nuclear Information System (INIS)

Data are presented on the monitoring of radioactive contamination of air and some foodstuffs at world (locations throughout Western South America, South Pacific, Africa during 1973. Data are included on the total β and γ activity and content of radionuclides found in fallout in air, milk and other environmental samples ( 131 I, 90 Sr, 137 Cs) [fr

Fifty years of atmospheric radioactivity monitoring by the German Meteorological Service

International Nuclear Information System (INIS)

2006-01-01

At a commemorative event at the Langen Training and Congress Center on 8 and 9 June 2005 it was brought to the attention of the audience that the German Meteorological Service has been charged with the sovereign task of monitoring atmospheric radioactivity since 8 August 1955. The purpose of this commission at the time was to measure traces of radioactivity in the atmosphere and precipitation and make forecasts on the movement of radioactive air masses. This was motivated by the above-ground nuclear tests carried out by the USA and the Soviet Union and the resulting measurable increase in atmospheric radioactivity levels. Equipped as it was with the necessary infrastructure the German Meteorological Service offered to take on this monitoring task. The importance of being able to assess the meteorological situation and provide data on radioactivity levels in the atmosphere and precipitation became apparent in 1986 after the reactor disaster of Chernobyl. When the Law on Preventive Radiation Protection was enacted in 1986 it was therefore only logical for the German Meteorological Service's commission to monitor atmospheric radioactivity levels to be renewed

Recovery of sludge from the treatment of liquid radioactive effluents by co-precipitation with calcium carbonate: laboratory study; Recuperation des boues de traitement des effluents radioactifs liquides par coprecipitation avec le carbonate de calcium: etude de laboratoire

Energy Technology Data Exchange (ETDEWEB)

Patti, F.; Gailledreau, C.; Cohen, P.

1961-02-24

As during the treatment by co-precipitation with calcium carbonate of liquid radioactive residues, a partial decontamination can be obtained by simply agitating an already formed radioactive sludge with the effluent to be processed, the authors study whether it would be possible to first perform a co-precipitation with a lower dose of calcium carbonate and then to complete decontamination by agitating with an adequate quantity of sludge stored during preceding operations. The authors report the study of the influence of reactant quantity on the chemical treatment efficiency, of the evolution of the activity of a radioactive residual solution in contact with a precipitate, of the cleaner element, of a precipitate reuse, of the technological and economic aspects, and of another possibility of reduction of the precipitate volume [French] Dans le traitement par coprecipitation avec le carbonate de calcium des residus radioactifs liquides, une decontamination partielle peut etre obtenue en agitant simplement une boue radioactive deja formee avec l'effluent a traiter. En consequence, il pourrait etre possible d'effectuer d'abord une coprecipitation avec une dose plus faible de carbonate de calcium et de completer ensuite la decontamination en agitant le liquide avec une quantite convenable de boue stockee a partir d'operations precedentes. (auteurs)

Studies on radioactivity monitoring proceedure for marine organisms

International Nuclear Information System (INIS)

Koyanagi, Taku; Hirano, Shigeki

1978-01-01

Suitability of several species of mollusca and seaweeds as indicator organisms for radioactivity monitoring of marine environment was examined by radioisotope tracer experiments or stable elements analyses from the standpoints of the affinities for radionuclides, the sampling procedures, and the distribution of radioactive and stable elements in the body of these organisms. Extremely high concentration factor of 54 Mn was shown by kidney of scallop suggesting the suitability for the efficient monitoring of the nuclide though the contribution of kidney to the weight of scallop was very small. Higher concentration of 54 Mn in midgut gland rather than kidney was observed in the case of other species of shellfishes but distribution of the nuclide among organs or tissues of the organisms varied during the period of intake and excretion. Ununiform distribution of radioactive and stable elements among the species of seaweeds and in the body of seaweeds observed by the tracer experiments and stable element analyses suggested the necessity of careful selection of the samples for monitoring of these nuclides. From the results of tracer experiments carried out in order to elucidate the relation between existing state of radionuclides in seawater and uptake by marine organisms, it was supposed that the complexed forms with inorganic or organic ligands in seawater were predominant species of radioactive cerium in seawater. (author)

The effluent problem in a plutonium production centre; Probleme des effluents d'un centre de production de plutonium

Energy Technology Data Exchange (ETDEWEB)

Galley, R; Cantel, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [French] La premiere partie du rapport est consacree a quelques generalites: situation geographique du Centre de Marcoule, provenance des effluents radioactifs, methodes de traitement de ces effluents. Dans la seconde partie, les auteurs presentent une description detaillee des diverses installations de la Station de Traitement des Effluents radioactifs du Centre de Marcoule et precisent les conditions de rejet dans le Rhone des effluents radioactifs traites. Quelques lignes sont consacrees aux comparaisons entre les resultats de l'exploitation des installations jusqu'en mai 1959 et les previsions publiees par les memes auteurs a l'occasion de la Conference de Bruxelles (1956). En conclusion, les auteurs donnent quelques principes essentiels, applicables a l'etude de nouvelles installations. (auteur)

Processing radioactive effluents with ion-exchanging resins: study of result extrapolation; Traitement des effluents radioactifs par resines echangeuses d'ions: etude de l'extrapolation des resultats

Energy Technology Data Exchange (ETDEWEB)

Wormser, G.

1960-05-03

As a previous study showed the ion-exchanging resins could be used in Saclay for the treatment of radioactive effluents, the author reports a study which aimed at investigating to which extent thus obtained results could be extrapolated to the case of higher industrial columns. The author reports experiments which aimed at determining extrapolation modes which could be used for columns of organic resin used for radioactive effluent decontamination. He notably studied whether the Hiester and Vermeulen extrapolation law could be applied. Experiments are performed at constant percolation flow rate, at varying flow rate, and at constant flow rate [French] Plusieurs etudes ont ete faites dans le but d'examiner les possibilites d'emploi des resines echangeuses d'ions pour le traitement des effluents radioactifs. Dans un rapport preliminaire, nous avons montre dans quelles limites un tel procede pouvait etre utilise au Centre d'Etudes Nucleaires de Saclay. Les essais ont ete effectues sur des petites colonnes de resine au laboratoire; il est apparu ensuite necessaire de prevoir dans quelle mesure les resultats ainsi obtenus peuvent etre extrapoles a des colonnes industrielles, de plus grande hauteur. Les experiences dont les resultats sont exposes dans ce rapport, ont pour but de determiner les modes d'extrapolation qui pourraient etre employes pour des colonnes de resine organique utilisees pour la decontamination d'effluents radioactifs. Nous avons en particulier recherche si la loi d'extrapolation de Hiester et Vermeulen qui donne de bons resultats dans le cas de fixation d'ions radioactifs en presence d'un ion macrocomposant sur des terres, pouvait etre appliquee. Les experiences, en nombre limite, ont montre que la loi d'extrapolation de Hiester et Vermeulen pouvait s'appliquer dans le cas de l'effluent considere quand les debits de percolation sont tres faibles; quand ils sont plus forts, les volumes de liquide percoles, a fixation egale, sont proportionnels aux

Environmental monitoring for radioactivity in Scotland, 1983 to 1987

International Nuclear Information System (INIS)

1989-01-01

This bulletin, which has been prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The results presented cover the period 1983 to 1987. The first section of the bulletin draws together the results of the monitoring and presents the principal conclusions; the second section summarises the procedures underlying the monitoring; and the remaining sections present detailed monitoring results. The principal conclusions of this bulletin are that: public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits including the ICRP's recommended principal limit of 1 millisievert per year; the levels of radiation exposure have been consistent with the recommendation of the NRPB that procedures leading to exposure of the public should be controlled so that the life-time effective dose equivalent does not exceed 70 millisieverts; any doses received have been small and correspond to negligible levels of risk to individuals; and the effects of waste disposals have been limited in accordance with the national standards of radiological safety, which are designed to protect the population from the harmful effects of radiation. (author)

Measurement of actinides in samples from effluent air, primary coolant and effluent water of nuclear power stations in the Federal Republic of Germany

International Nuclear Information System (INIS)

Winkler, R.; Hoetzl, H.; Rosner, G.

1977-01-01

Since the middle of 1973 the alpha radioactivity of a number of aerosol filters from the stack monitoring systems of some nuclear power stations, of water effluent samples from all german nuclear power stations and of samples from the primary coolant water of one nuclear power reactor was measured. Essentially, the following procedures of sample preparation for alpha spectrometry of the samples in large area gridded ionization chambers were used; cold ashing of the aerosol samples in 'excited' oxygen, coprecipitation of the alpha emitters from the effluent water samples with iron hydroxide and subsequent cold ashing of the precipitate, and evaporation of the samples from the primary cycle on stainless steel plates. The following transuranium nuclides, or some of them, were found in the samples of the primary coolant and in several aerosol filter samples: Pu-239/240, Pu-238 and/or Am-241, Cm-242 and Cm-244. Cm-242 contributes most to the alpha radioactivity in fresh samples. In the effluent water samples Cm-242, Pu-239/240 and Pu-238 and/or Am-241 were identified in some cases, in one case also Cm-244. Detection limits of the procedures used for the analysis of the above stated transuranium nuclides were in the order of 0,1 fCi per m 3 for the aerosol samples and of 0.2 pCi per 1 for the liquid samples. For the effluent air and water samples in most cases specific activities near the detection limit or somewhat higher were found. On the basis of the measurements, an estimation of the annual actinides releases from nuclear power stations in the Federal Republic of Germany is given

Radioactivity Monitoring of the Irish Environment 2010-2011

International Nuclear Information System (INIS)

McGinnity, P.; Currivan, L.; Dowdall, A.; Hanley, O.; Kelleher, K.; McKittrick, L.; Pollard, D.; Somerville, S.; Wong, J.; McMahon, C.

2012-11-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland RPII during 2010 and 2011. The RPII has routinely monitored levels of radioactivity in the Irish environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The data presented in this report confirm that while the levels of artificial radioactivity in the Irish environment are detectable, they are low. They do not pose a significant risk to the human health of the Irish population. Trace amounts of radioactive isotopes consistent with the Fukushima nuclear accident were detected in air, rainwater and milk samples during the period March to May 2011. These increases in levels of radioactivity were not of concern from a public health point of view. For the remainder of the reporting period, activity concentrations of radionuclides in airborne particles were low and consistent with measurements made in recent years. Radioactivity levels in milk, mixed diet and a wide range of foodstuffs were low and, for the majority of samples, below the detection limits. All drinking waters tested were found to be in compliance with the total indicative dose defined in national and EU legislation. The doses incurred by the Irish public in 2010 and 2011 as a result of artificial radioactivity in the marine environment are small when compared to dose limits or to natural radiation doses received by the Irish public. The doses to the most exposed individuals, members of the oyster and mussel farmers critical group, were approximately 0.02 per cent and 0.05 per cent of the annual dose limit of 1000 microsieverts for members of the public from practices involving controllable sources of radiation in 2010 and

Occupational monitoring at radioactive waste deposit

Energy Technology Data Exchange (ETDEWEB)

Pereira, Wagner S.; Cunha, Franklin S. [Indústrias Nucleares do Brasil (COMAP.N/FCN/INB), Resende, RJ (Brazil). Fábrica de Combustível Nuclear. Coordenação de Meio Ambiente e Proteção Radiológica Ambiental; Kelecom, Alphonse [Universidade Federal Fluminense (LARARA-PLS/UFF), Niterói, RJ (Brazil). Lab. de Radiobiologia e Radiometria Pedro Lopes dos Santos; Silva, Ademir X., E-mail: pereiraws@gmail.com, E-mail: wspereira@inb.gov.br, E-mail: franklincunha@inb.gov.br, E-mail: lararapls@hotmail.com, E-mail: Ademir@nuclear.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2017-07-01

The Initial Deposit of Low Activity Radioactive Waste - DIRBA is an ancillary facility to the Nuclear Fuel Factory - FCN for the initial storage of low activity radioactive waste generated in the nuclear fuel cycle under the responsibility of the FCN. Currently approximately 460 200-liter drums containing Class 2.3 waste are stored: Waste containing Natural Radionuclides (RBMN-RN). As part of the nuclear licensing of the facility, an area radiological monitoring program was developed with monthly monitoring of 17 exposure points, 3 direct long-distance air sampling points with CAM alpha-7 monitors, monitored in January and 9 points where smears of alpha long half-life emitters were monitored in January. The mean exposure rate between points was 0.5 μSv∙h{sup -1}, with a maximum of 1.27 μSv∙h{sup -1} varying, on average, between 0.98 μSv∙h{sup -1} at point P1 to 0.23 μSv∙h{sup -1} at P11. The monthly average was the same, 0.50 μSv∙h-1, ranging from 0.46 μSv∙h{sup -1} (November) to 0.57 μSv∙h{sup -1} (August). The half-life long-lived alpha sampling were all below the MDA as well as the 9 smears. Regarding the requirements of monitored areas, the deposit must be considered as supervised area, from the point of view of radioprotection. The possibility of tipping the drums or other accidents with spillage of material contained into them caused, in a proactive way, the area to be considered a controlled area. (author)

Toxicity regulation of radioactive liquid waste effluent from CANDU stations - lessons from Ontario's MISA program

International Nuclear Information System (INIS)

Rodgers, D.W.

2009-01-01

Toxicity testing became an issue for Ontario's CANDU stations, when it was required under Ontario's MISA regulations for the Electricity Generation Sector. In initial tests, radioactive liquid waste (RLW) effluent was intermittently toxic to both rainbow trout and Daphnia. Significant differences in RLW toxicity were apparent among stations and contributing streams. Specific treatment systems were designed for three stations, with the fourth electing to use existing treatment systems. Stations now use a combination of chemical analysis and treatment to regulate RLW toxicity. Studies of Ontario CANDU stations provide a basis for minimizing costs and environmental effects of new nuclear stations. (author)

Experiment of decontamination of radioactive liquid by a biological method

International Nuclear Information System (INIS)

Wormser, G.

1962-01-01

The author reports experiments of treatment of radioactive liquid effluents by percolation on a bacterial bed like the one used for the treatment of sewer wastewaters. He also reports results obtained in other countries in terms of reduction of effluent radioactivity for various radioactive ions. The installation is described and results are presented in terms of variation of contamination of an effluent with respect to its recycling on a bacterial bed [fr

Environmental monitoring program of CDTN

International Nuclear Information System (INIS)

Ferreira, E.G.

1985-09-01

This environmental monitoring program of CDTN aim to do a survey that permit to verify if the radioactive wastes release by CDTN agree with basic rudiments of radioprotection, evaluate the environmental impact, verify the adjustment of using proceedings to effluents control, to evaluate the maximum radiation doses that public persons will be able to get yearly. (C.M.) [pt

Evaluation 2000 and regulation and method. Release monitoring and environmental surveillance around Cea centers; Bilan 2000 et reglementation et methode. Controle des rejets et surveillance de l'environnement des centres CEA

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-06-01

This publication counts for the year 2000 for the evaluation of liquid and gaseous radioactive effluents releases and the radioactivity levels measured in the vicinity of Cea centers, through the air, water, vegetation and milk surveillance. An analysis of the results from 1996 to 2000 allows to follow their evolution. A second booklet develops the sampling and measurement methods made on effluents in environment. It present besides the regulation applied to effluents monitoring. (N.C.)

The treatment of effluents

International Nuclear Information System (INIS)

Wormser, G.; Rodier, J.; Robien, E. de; Fernandez, N.

1964-01-01

For several years the French Atomic Energy Commission has been studying with interest problems presented by radio-active effluents. Since high activities have not yet received a definite solution we will deal only, in this paper, with the achievements and research concerning low and medium activity effluents. In the field of the achievements, we may mention the various effluent treatment stations which have been built in France; a brief list will be given together with an outline of their main new features. Thus in particular the latest treatment stations put into operation (Grenoble, Fontenay-aux-Roses, Cadarache) will be presented. From all these recent achievements three subjects will be dealt with in more detail. 1 - The workshop for treating with bitumen the sludge obtained after concentration of radionuclides. 2 - The workshop for treating radioactive solid waste by incineration. 3 - A unit for concentrating radio-active liquid effluents by evaporation. In the field of research, several topics have been undertaken, a list will be given. In most cases the research concerns the concentration of radionuclides with a view to a practical and low cost storage, a concentration involving an efficient decontamination of the aqueous liquids in the best possible economic conditions. For improving the treatments leading to the concentration of nuclides, our research has naturally been concerned with perfecting the treatments used in France: coprecipitation and evaporation. In our work we have taken into account in particular two conditions laid down in the French Centres. 1 - A very strict sorting out of the effluents at their source in order to limit in each category the volume of liquid to be dealt with. 2 - The necessity for a very complete decontamination due to the high population density in our country. In the last past we present two original methods for treating liquid effluents. 1 - The use of ion-exchange resins for liquids containing relatively many salts. The

Report of radioactivity survey research in fiscal year 1988

International Nuclear Information System (INIS)

1989-12-01

The National Institute of Radiological Sciences has been surveyed, as part of the radioactivity research project by the Science and Technology Agency, radioactivity levels in the environment and safety analysis for radioactive fallouts associated with nuclear weapons tests since 1959 and effluents from nuclear installations. With a remarkable advent of the peaceful applications of radionuclides, radioactivity in the environment has been becoming a matter of concern for the population in Japan. Radioactivity research is considered to become more important because it may provide clues for the basis of its influences upon the human body and environment. This report gives a survey of the radioactivity research project performed in the fiscal year 1988. The following topics are covered: (1) radioactivity levels and dosimetry in the environment, foods, and human body; (2) radioactivity levels surrounding nuclear installations; (3) services in the Radioactivity Survey Data Center; (4) basic survey of evaluation for the results of radioactivity levels; (5) training of technichians for monitoring environmental radioactivity; and (6) survey research for dosimetry and countermeasures at emergency. (N.K.)

Environmental and effluent monitoring at ANSTO sites, 1999

Energy Technology Data Exchange (ETDEWEB)

Hoffman, E L; Loosz, T; Mokhber-Shahin, L

1999-07-01

Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the I milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron (authors)

Environmental and effluent monitoring at ANSTO sites 1999

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, E L; Loosz, T; Mokhber-Shahin, L [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW, Australia, (Australia)

2000-07-01

Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the 1 millisievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron.

Environmental and effluent monitoring at ANSTO sites, 2000

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, E L; Loosz, T; Mokhber-Shahin, L [Australian Nuclear Science and Technology Organisation, Menai, NSW (Australia)

2001-07-01

Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2000 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 2000 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2000 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1 % of the 1 milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron.

Environmental and effluent monitoring at ANSTO sites, 2000

International Nuclear Information System (INIS)

Hoffmann, E.L.; Loosz, T.; Mokhber-Shahin, L.

2001-01-01

Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2000 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 2000 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2000 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1 % of the 1 milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron

Environmental and effluent monitoring at ANSTO sites 1999

International Nuclear Information System (INIS)

Hoffmann, E. L.; Loosz, T.; Mokhber-Shahin, L.

2000-01-01

Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the 1 millisievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron

Environmental and effluent monitoring at ANSTO sites, 1999

International Nuclear Information System (INIS)

Hoffman, E.L.; Loosz, T.; Mokhber-Shahin, L.

1999-01-01

Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the I milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron (authors)

Radiation Measurements Laboratory (RML) calibration and assessment of the ATR SPING-3 stack effluent monitor

International Nuclear Information System (INIS)

Koeppen, L.D.; Rogers, J.W.; Simpson, O.D.

1983-12-01

An evaluation, calibration and assessment of the Eberline SPING-3 ATR stack effluent monitor was conducted. This unit which monitors particulate, iodine and noble gas effluents was producing abnormal results following the initial installation and operational testing. The purposes of this work were to find the causes of the abnormal results and correct them if possible; check the calibrations and adjust them if necessary; and to provide a better in-depth understanding of what the unit is monitoring and how well it performs under this application. Results have shown that there were some problems associated with the unit as initially installed and tested. These problems have been identified and suggested alternatives shown, the monitor was found to be applicable to some extent under the current conditions. The calibrations have been checked and adjustments made. More operation testing and evaluation is needed to assess how well this works under a variety of ATR operating conditions. 2 references, 10 figures, 3 tables

30 years of monitoring environmental radioactivity in the Federal Republic of Germany

International Nuclear Information System (INIS)

1985-01-01

The individual sections of the report describe the development of monitoring functions and of the contamination of the atmosphere and the biosphere by radioactive substances. After environmental radioactivity due to the fallout of nuclear explosions reached a peak level in 1963, its contribution to radiation exposure today is insignificant in comparison with natural radioactivity. Moreover, monitoring by authorities of the emissions and the environmental impact of nuclear installations has been extended during the past 20 years in such a way that the existing network of measuring stations takes full account of the increased number of nuclear installations. The monitoring results show that nuclear installations do not make any considerable contribution to environmental radioactivity. (orig./PW) [de

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000.

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

International Nuclear Information System (INIS)

2002-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000

Evaluation of environmental radioactivity monitoring data around the Kartini Reactor area

International Nuclear Information System (INIS)

Yazid, M; Sutrisno; Sukarman-Aminjoyo; Zaenal-Abidin

1996-01-01

Evaluation of environmental radioactivity monitoring data around the Kartini Reactor area has been done. The aim of this investigation is for tracing the possibility of radioactivity released in the environment during the operation of Kartini reactor. The data was evaluated were monthly monitored data taken from 1986 to 1994 period. The method of analysis was done by comparing the environmental radioactivity data before and after reactor commissioning, off side the reactor up to a radius of 5.000 meters and more than 5.000 meters from Kartini reactor and also compared to the maximum permissible radioactivity according to the current regulation. This evaluation showed that there was no indication of radioactivity release to the environment during this period of reactor operation

Radioactive contamination in monitors received for calibration

International Nuclear Information System (INIS)

Dias, Paulo S.; Santos, Gilvan C. dos; Brunelo, Maria Antonieta G.; Paula, Tiago C. de; Pires, Marina A.; Borges, Jose C.

2013-01-01

The Calibration Laboratory - LABCAL, from the Research Center for Metrology and Testing - METROBRAS, MRA Comercio de Instrumentos Eletronicos Ltda., began activities in October 2008 and, in August 2009, decided to establish a procedure for monitoring tests, external and internal, of all packages received from customers, containing instruments for calibration. The aim was to investigate possible contamination radioactive on these instruments. On July 2011, this procedure was extended to packagings of personal thermoluminescent dosemeters - TLD, received by the newly created Laboratory Laboratorio de Dosimetria Pessoal - LDP . In the monitoring procedure were used monitors with external probe, type pancake, MRA brand, models GP - 500 and MIR 7028. During the 37 months in which this investigation was conducted, were detected 42 cases of radioactive contamination, with the following characteristics: 1) just one case was personal dosimeter, TLD type; 2) just one case was not from a packing from nuclear medicine service - was from a mining company; 3) contamination occurred on packs and instruments, located and/or widespread; 4) contamination values ranged from slightly above the level of background radiation to about a thousand fold. Although METROBRAS has facilities for decontamination, in most cases, especially those of higher contamination, the procedure followed was to store the contaminated material in a room used for storage of radioactive sources. Periodically, each package and/or instrument was monitored, being released when the radiation level matched the background radiation. Every contamination detected, the client and/or owner of the instrument was informed. The Brazilian National Energy Commission - CNEN, was informed, during your public consultation for reviewing the standard for nuclear medicine services, held in mid-2012, having received from METROBRAS the statistical data available at the time. The high frequency of contamination detected and the high

ANSTO's radioactive waste management policy. Preliminary environmental review

International Nuclear Information System (INIS)

Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

1996-05-01

For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs

Monitoring of radioactivity in the environment 201

International Nuclear Information System (INIS)

Moeller, B.; Dyve, J.E.; Tazmini, K.

2013-01-01

The Report summarizes the data from Norwegian Radiation Protection Authority and The Norwegian Civil Defence monitoring programs for radioactivity in the environment in 2011. A short description of the systems is also presented.(Author)

Roshydromet system of environment radioactive contamination monitoring in the Arctic region of Russia

International Nuclear Information System (INIS)

Chelukanov, V.

1995-01-01

159 arctic hydrometerological stations take measurements of gamma radiation. 51 stations monitor the density of atmospheric radioactive fallout and 12 stations monitor the concentration of aerosols. 13 hydrological stations sited in the mouths of main Arctic Ocean rivers take water samples. Regional laboratories carry out isotop analysis of samples. Information on high levels of a radioactivity measured at the monitoring stations, as well as information on abnormal radioactivity from regional laboratories are transmitted to the Information Centers on the monitoring system (Moscow and Obnisk) by cable. 2 figs., 1 tab

Application of reverse osmosis to the treatment of liquid effluents produced by nuclear power plants

International Nuclear Information System (INIS)

Huet, Y.; Poulat, B.; Menjeaud, C.

1989-01-01

Radioactive liquid effluents generated during the operation of PWR nuclear power units are currently treated by two independent systems. The effluents from the reactor coolant system are recycled, unlike the others, which, after treatment, are released into the river or ocean that provides cooling water for the unit. The objective of the treatment of nonrecycled effluents is to separate from them as much of the radioactive particles that they contain as possible, so as to release into the environment a maximum volume of nonradioactive waste, and to be left with only a minimum volume of concentrated waste, containing most of the initial radioactivity, which must be loaded into casks for storage. Membrane-based filtration techniques, because they have excellent separation performances, can logically be used for this decontamination of the liquid effluents. Having developed its own reverse osmosis membrane, a possible application in a nuclear power plant, i.e., integration of a reverse osmosis unit into a radioactive liquid effluent treatment system is presented. (author)

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2002-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2002 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 19 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2003-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2003 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137} Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 22 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 10 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

International Nuclear Information System (INIS)

Lee, Byung Ki.; Hwang, Sang Kyu

2001-12-01

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of 7 Be and 137 Cs on airborne dust, and 7 Be, 40 K and 137 Cs on fallout, precipitation have been analyzed monthly. The 7 Be, 40 K, 137 Cs and 226 Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of 7 Be, 40 K, and 137 Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except 40 K nuclide. All the concentrations of 137 Cs and 226 Ra nuclides in the water are less than the MDA values

Radiotracer investigations on dispersion of low level effluents discharged into Mumbai Harbour Bay

International Nuclear Information System (INIS)

Jacob, Noble; Mendhekar, G.N.; Singh, Sanjay

2015-01-01

Two radiotracer investigations (using radioactive 82 Br) were carried out near the CIRUS jetty in the Mumbai Harbour Bay (MHB) to evaluate the dilution and dispersion of low level liquid effluents discharged from the BARC Effluent Treatment Plant (ETP). The first experiment was conducted during an ebb tide while the second was conducted during a flood tide. In both the experiments, about 1.55Ci (57 GBq) of 82 Br was injected into one of the aeration tanks of the ETP. The labelled effluent was discharged into the bay and the movement of the plume in the coastal water was monitored using underwater γ-scintillation detectors. Contour map depicting the spread of the radioactive plume was prepared and dilution factors were estimated. The extent of spread of the tracer was comparatively higher during the ebb tide than in flood tide. A 2-D advection dispersion (analytical) model was used to obtain the system parameters D x and D y (for the ebb tide D x is ∼ 5 m 2 s -1 and D y : 0.7 m 2 s -1 ; for flood tide D x is 5 m 2 s -1 and D y : 0.15 m 2 s -1 ). (author)

Morsleben repository for radioactive waste (ERAM). Operational safety, radiation protection and environmental monitoring. Release: December 2009

International Nuclear Information System (INIS)

2010-01-01

The report overviews the monitoring activities of the Federal Office for Radiation Protection at the Morsleben repository for radioactive waste (ERAM), focussing the ERAM inventory of radioactive waste and the measures and results of geomechanical and hydrogeological monitoring, operational radiation protection, the monitoring of discharges of radioactive substances, environmental monitoring, and the dose levels expected from discharges of radioactive substances. (orig.)

Environmental and effluent monitoring at ANSTO sites, 2005-2006

International Nuclear Information System (INIS)

Hoffmann, Emmy L.; Loosz, Tom; Ferris, John M.; Harrison, Jennifer J.

2006-01-01

This report presents the results of ANSTO's environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) sites, from July 2005 to June 2006. Estimated effective doses to the critical group of members of the public potentially affected by routine airborne emissions from the LHSTC were less than 0.005 mSv/year. The maximum potential dose was 23% of the ANSTO ALARA objective of 0.02 mSv/year, much lower than the public dose limit of 1 mSv/year that is recommended by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The effective doses to the critical group of members of the public potentially exposed to routine liquid effluent releases from the LHSTC have been realistically estimated as a quarter (or less) of the estimated doses to the critical group for airborne releases. The median tritium concentrations detected in groundwater and surface waters at the LHSTC were typically less than 2% of those set out in the Australian Drinking Water Guidelines. The airborne emissions from the NMC were below the ARPANSA-approved notification levels. Results of environmental monitoring at both ANSTO sites confirm that the facilities continue to be operated well within regulatory limits. ANSTO's routine operations at the LHSTC and NMC make only a very small addition to the natural background radiation dose of -1.5 mSv/year experienced by members of the Australian public

Portsmouth Gaseous Diffusion Plant environmental monitoring report for calendar year 1981

International Nuclear Information System (INIS)

Acox, T.A.; Anderson, R.E.; Hary, L.F.; Klein, L.S.; Vausher, A.L.

1982-04-01

At the Portsmouth Gaseous Diffusion Plant all effluent streams are sampled regularly and analyzed to assess compliance with applicable environmental standards. Radioactivity is measured in air, water, food, soil, and sediments; and radiation doses to the public are calculated. All public radiation doses from process effluents are well within Department of Energy and US EPA standards. Non-radioactive effluents either presently comply with federal standards or will comply upon completion of planned projects. The environmental impact of effluents from cleaning and decontamination operations has been reduced through flow reduction and improved chemical treatment. CY-1981 was the first full year under a new National Pollutant Discharge. Elimination System (NPDES) permit for liquid effluents; compliance with the permit's discharge limits did not present any significant problems. Engineering is proceeding on projects to be constructed through 1985 to further reduce the impact of liquid effluents. A new licensed sanitary landfill utilizing the area fill method went into operation in July 1981. Although neither the State of Ohio nor the federal government has established standards for fluoride in the atmosphere or in vegetation, fluorides are monitored because they are used extensively in the gaseous diffusion process

Stack Monitor Operating Experience Review

International Nuclear Information System (INIS)

Cadwallader, L.C.; Bruyere, S.A.

2009-01-01

Stack monitors are used to sense radioactive particulates and gases in effluent air being vented from rooms of nuclear facilities. These monitors record the levels and types of effluents to the environment. This paper presents the results of a stack monitor operating experience review of the U.S. Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS) database records from the past 18 years. Regulations regarding these monitors are briefly described. Operating experiences reported by the U.S. DOE and in engineering literature sources were reviewed to determine the strengths and weaknesses of these monitors. Electrical faults, radiation instrumentation faults, and human errors are the three leading causes of failures. A representative 'all modes' failure rate is 1E-04/hr. Repair time estimates vary from an average repair time of 17.5 hours (with spare parts on hand) to 160 hours (without spare parts on hand). These data should support the use of stack monitors in any nuclear facility, including the National Ignition Facility and the international ITER project.

Shore and off-shore monitoring of Rana Pratap Sagar lake

International Nuclear Information System (INIS)

Verma, P.C.; Roy, Alpana; Hegde, A.G.

2005-01-01

The Rana Pratap Sagar (RPS) is a man made fresh water reservoir on the river Chambal and is located about 65 km away from Kota city in the state of Rajasthan. It is a balancing reservoir between Gandhi Sagar, upstream and Jawahar Sagar, downstream. On the eastern bank of RPS there exist Rajasthan Atomic Power Station (RAPS) Site, comprising of four operating pressurized Heavy Water Reactors (PHWRs) of 220 MWe each. The low level radioactive effluents from RAPS, are released in controlled manner to RPS. On release the effluents undergo dispersion in the aquatic environment of RPS and may reach man through, various pathways. Being fresh water reservoir, considerable emphasis is laid on the aquatic monitoring aspects relating to RPS and downstream reservoirs. This paper presents the monitored levels of radioactivity prevailing in the aquatic samples collected from near shore and off shore locations of RPS. (author)

Status of 2009 radioactivity monitoring in French Polynesia. Results of IRSN's monitoring network

International Nuclear Information System (INIS)

2010-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes, consists in regularly collecting samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of that territory. They come from the marine environment of the open sea, from the marine lagoon environment and from the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Environment Study and Monitoring, based in Vairao, Tahiti Island. The 239 samples collected in 2009 were measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes have also been determined for 17 selected samples and tritium activities for 15 water samples. The results for the year 2009 are in the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro Sieverts per year). This value corresponds to less than 0, 5 % of exposure due to natural radioactivity in Polynesia (approximately 1000 μSv.y -1 ). (authors)

Waste Treatment Plant Liquid Effluent Treatability Evaluation

International Nuclear Information System (INIS)

LUECK, K.J.

2001-01-01

Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF

Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents; Essais d'emploi des resines organiques echangeuses de cations pour la decontamination des effluents aqueux radioactifs

Energy Technology Data Exchange (ETDEWEB)

Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

1962-12-14

The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [French] Dans ce rapport nous faisons le point des essais et resultats obtenus au laboratoire au cours d'une etude concernant l'utilisation des echangeurs d'ions synthetiques pour la decontamination des effluents radioactifs de niveau d'activite moyenne et de charge en sels non negligeable. Les resines sont employees sous forme sodique et regenerees apres chaque operation de fixation. Le regenerant decontamine et debarrasse de ses ions genants est utilise pour plusieurs operations d'elution. Les seuls residus a stocker proviennent d'une part eventuellement d'un pretraitement de l'effluent, d'autre part, dans tous les cas des precipites consecutifs a la purification de l'eluant dont le traitement chimique est plus aise et donne lieu a des boues beaucoup moins volumineuses qu'une coprecipitation effectuee sur la totalite de l'effluent. (auteurs)

Investigation on supervising and monitoring of major radioactive pollution source

International Nuclear Information System (INIS)

Zeng Yibing; Zhang Zongrang; Men Meng; Zhang Peng

2005-01-01

Objective: In order to optimize the supervisory monitoring proposal of the major radioactive enterprises. Methods: The authors have worked out the public doses within the range of 0-1 km as well as 1-2 km through monitoring analysis of the radioactive pollutant enterprises on the samples of its surrounding air, water, soil and organism. Results: Generally the pollutant range of the enterprises runs from 0 to 1.5 km. Conclusion: Unnecessary working hours can be shortened as long as we keep the routine supervisory monitor of pollutant enterprises within the range of 2 km. (authors)

A new stack effluent monitoring system at the Risoe Hot Cell plant

International Nuclear Information System (INIS)

Boetter-Jensen, L.; Hedemann Jensen, P.; Lauridsen, B.

1984-06-01

This report describes a new stack effluent monitoring system that has been installed at the Hot Cell facility. It is an integrating iodine/particulate system consisting of a γ-shielded flow house in which a continous air sample from the ventilation channel ia sucked through coal and glass filter papers. Activity is accumulated on the filter papers and a thin plastic scintillator detects the β-radiation from the trapped iodine or particulate activity. The stack effluent monitoring system has a two-step regulating function as applied to the ventilation system, first switching it to a recirculating mode, and finally to building-seal after given releases of 131 I. The collection efficiency for iodine in form of elementary iodine (I 2 ) and methyliodide (CH 3 I) has been determined experimentally. The unwanted response from a noble gas release has also been determined from experiments. The noble gas response was determined from puff releases of the nuclide 41 Ar in the concrete cells. It is concluded that the iodine/particulate system is extremely sensitive and that it can easily detect iodine or particulate releases as low as a few MBq. A gamma monitor placed in connection with the iodine/particulate system detects Xe/Kr-releases as low as a few tens of MBq per second. (author)

Survey monitoring of environmental radioactivity in Busan area

Energy Technology Data Exchange (ETDEWEB)

Yang, Han Soeb; Jang, Young A. [Busan Regional Monitoring Station, Busan (Korea, Republic of)

2003-12-15

At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Busan area

International Nuclear Information System (INIS)

Yang, Han Soeb; Jang, Young A.

2003-12-01

At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants

1984 Environmental monitoring program report for Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Dickson, R.L.

1985-05-01

The results of the various monitoring programs for 1984 indicated that radioactivity from INEL Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site; and it compares and evaluates the sample results, discussing implications, if any. The report also summarizes significant environmental activities at the INEL Site during 1984, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) groundwater monitoring program. 28 refs., 13 figs., 22 tabs

A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites

International Nuclear Information System (INIS)

Rego, J.H.; Smith, D.K.; Friensehner, A.V.

1995-01-01

The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for α, β and γ emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for γ and α/β monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in α/β liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure 241 Am produced from 241 Pu by β decay. Because 241 Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., 137 Cs)

Evaluating future detriment from radioactive discharges

International Nuclear Information System (INIS)

Fleishman, A.B.; Clark, M.J.

1982-01-01

A quantitative framework for expressing judgements on the relative valuation of both future protection costs and radiation detriment from radioactive discharges is discussed. The framework can be applied to a series of notional effluent control options, illustrating the sensitivity of optimum protection levels to variations in discount rates. Using data on the radiological significance and management of radioactive discharges arising from the nuclear fuel cycle, it was shown that this quantitative optimization method of evaluating future detriment has important implications for the management of radioactive effluents, particularly those containing long-lived nuclides. (U.K.)

Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

International Nuclear Information System (INIS)

Hummel, L.; Zech, J.B.

2005-01-01

Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

Environmental radioactive monitoring in Itu, Sao Paulo, Brazil

International Nuclear Information System (INIS)

1990-01-01

The results of the environmental monitoring of a region near to a radioactive materials deposit in Sao Paulo State, Brazil, are presented. The radioactive materials are uranium and thorium hydroxides from monazite processing. The temporal variation of 226 Ra was determined in the superficial and underground water, showing no increase for the former and a maximum concentration of 0,306 Bq/L for the latter. 21 figs., 17 tabs

Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor

International Nuclear Information System (INIS)

Tuca, C.; Stochioiu, A.; Sahagia, M.; Gurau, D.; Dragusin, M.

2015-01-01

This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes. - Highlights: • The DELs for gaseous and liquid effluents in decommissioning were studied. • The impact on the environment and critical group was assessed. • Gamma-ray spectrometry was used to determine the radionuclide composition. • Based on the dosimetry models, the values of conservative DELs were calculated. • The DELs are compliant for gases, not for liquids; require the treatment as rad-waste

ANSTO`s radioactive waste management policy. Preliminary environmental review

Energy Technology Data Exchange (ETDEWEB)

Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

1996-05-01

For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs.

Environmental monitoring report, 1974

International Nuclear Information System (INIS)

1975-01-01

Results are reported of the effluent and environmental monitoring programs at the Pinellas Plant during 1974. Sample analyses revealed the on-site sewage treatment facility operated well within State of Florida Standards. Likewise, offsite discharges met the applicable standards for arsenic, biochemical oxygen demand, chlorides, chromium, copper, cyanides, detergents, dissolved oxygen, dissolved solids, fluorides, lead, mercury, nitrogen, oils and greases, phenols, pH, phosphorus, suspended solids, turbidity and zinc. The results of iron and specific conductance analyses showed levels in excess of state standards and are discussed in the body of the report. In addition to the non-radioactive parameters listed above, a small quantity of radioactive tritium oxide was released in the plant's liquid effluent. Small quantities of tritium gas, tritium oxide, and krypton-85 gas were released from the plant during the year. Average ground level concentrations of these radioisotopes were all significantly less than 1 percent of recommended guide for continuous nonoccupational exposure. (U.S.)

Monitoring and assessment of radiation exposure from routine radioactive discharges, and its relevance to the question of disease clusters

International Nuclear Information System (INIS)

Jones, S.R.

1989-01-01

Over the period of more than 30 years in which nuclear facilities have been operating, monitoring of the environment around such facilities has produced a wealth of information about the levels of radioactivity in the environment and about how radioactivity, introduced into the environment from effluent discharges, behaves in natural systems. Techniques for estimating radiation exposure to people from environmental measurements, or from theoretical models relating discharges to radiation exposure, have also been developed and validated where possible. The existence of localised excesses of leukaemia near the reprocessing plants at Sellafield and Dounreay, which cannot be explained on the basis of radiation exposure using these established methodologies, could be taken to imply that the methodologies are defective. However the radiation risk estimates have been shown to be robust to many of the suggested deficiencies and there are other, more qualitative, indications that discharges may not be a causative factor. It is argued that a broader search for possible causative factors may be more productive in resolving the conundrum. (author)

Environmental and effluent monitoring at ANSTO sites, 2001

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, E L; Loosz, T

2002-07-01

Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2001 at the two sites owned and operated by ANSTO at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC-controlled airborne discharges were estimated for 2001 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2001 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This is well below the ALARA objective of 0.02 mSv per year for off-site doses that ANSTO has set and much lower than the public dose limit of 1 mSv per year (above natural background and medical doses) and the natural background dose in Australia of 1.5 mSv per year (Webb et al; 1999). It is concluded that there is no impact on the health of the community as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron.

Environmental and effluent monitoring at ANSTO sites, 2001

International Nuclear Information System (INIS)

Hoffmann, E.L.; Loosz, T.

2002-01-01

Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2001 at the two sites owned and operated by ANSTO at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC-controlled airborne discharges were estimated for 2001 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2001 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This is well below the ALARA objective of 0.02 mSv per year for off-site doses that ANSTO has set and much lower than the public dose limit of 1 mSv per year (above natural background and medical doses) and the natural background dose in Australia of 1.5 mSv per year (Webb et al; 1999). It is concluded that there is no impact on the health of the community as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2001-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs and {sup 226}Ra nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2000-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2000 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussed) and 5 tap water sampled in Youngsoe area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA value, except {sup 40}K nuclide. The concentrations of {sup 137}Cs and {sup 226}Ra nuclide in tap water are less(or is slightly higher in one sample) than the MDA value.

Ambient radioactivity monitoring V: Marine environment, fish and marine organisms

International Nuclear Information System (INIS)

Wedekind, C.; Kanisch, G.

1996-01-01

The sea, originally thought to have an almost unlimited capacity of uptake of pollutants due to its water volumes available for dilution, was shown by growing insight into the physical, chemical and ecologic interdependencies to be a sensitive ecosystem. Its limits to cope with growing pollution are increasingly becoming clear, and this is a particular reason to perform radioactivity monitoring of the sea water, as radioactivity is transferred to the marine organisms. Organisms selected for monitoring are fish and crustaceans. (orig.) [de

Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

International Nuclear Information System (INIS)

1993-01-01

This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

International Nuclear Information System (INIS)

1991-01-01

This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

International Nuclear Information System (INIS)

1991-01-01

This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

Biological sampling for marine radioactivity monitoring

International Nuclear Information System (INIS)

Fowler, S.W.

1997-01-01

Strategies and methodologies for using marine organisms to monitor radioactivity in marine waters are presented. When the criteria for monitoring radioactivity is to determine routes of radionuclide transfer to man, the ''critical pathway'' approach is often applied. Alternatively, where information on ambient radionuclide levels and distributions is sought, the approach of selecting marine organisms as ''bioindicators'' of radioactivity is generally used. Whichever approach is applied, a great deal of knowledge is required about the physiology and ecology of the specific organism chosen. In addition, several criteria for qualifying as a bioindicator species are discussed; e.g., it must be a sedentary species which reflects the ambient radionuclide concentration at a given site, sufficiently long-lived to allow long-term temporal sampling, widely distributed to allow spatial comparisons, able to bioconcentrate the radionuclide to a relatively high degree, while showing a simple correlation between radionuclide content in its tissues with that in the surrounding waters. Useful hints on the appropriate species to use and the best way to collect and prepare organisms for radioanalysis are also given. It is concluded that benthic algae and bivalve molluscs generally offer the greatest potential for use as a ''bioindicator'' species in radionuclide biomonitoring programmes. Where knowledge on contribution to radiological dose is required, specific edible marine species should be the organisms of choice; however, both purposes can be served when the edible species chosen through critical pathway analysis is also an excellent bioaccumulator of the radionuclide of interest. (author)

Survey monitoring of environmental radioactivity in Gunsan area

Energy Technology Data Exchange (ETDEWEB)

Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

2001-01-15

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2000 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant Changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are I fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Gunsan area

Energy Technology Data Exchange (ETDEWEB)

Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

2002-12-15

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Gunsan area

International Nuclear Information System (INIS)

Kim, Byoung Ho; Ro, Jeong Suk

2002-12-01

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of 137 Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants

Revision of by-laws about effluents of EdF's nuclear power plants

International Nuclear Information System (INIS)

2002-01-01

In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, 14 C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

Portsmouth Uranium Enrichment Complex environmental monitoring report for calendar year 1985

International Nuclear Information System (INIS)

1986-05-01

At the Portsmouth Uranium Enrichment Complex all effluent streams are sampled regularly and analyzed to assess compliance with applicable environmental standards. Radioactivity is measured in air, water, fish, produce, soil, sediments and vegetation; and radiation doses to the public are calculated. The calculated public radiation doses from process effluents are within US Department of Energy (DOE) and US Environmental protection Agency (USEPA) standards. An extensive amount of engineering effort is underway to modify existing airborne radioactivity emissions sources to further reduce emissions in compliance with DOE policy. Non-radioactive effluents either presently comply with federal standards or will comply upon completion of planned projects. CY-1985 was the fifth full year under the current National Pullutant Discharge Elimination System (NPDES) permit for liquid effluents, and the third year since the Ohio Environmental Protection Agency (OEPA) assumed responsibility for administering the NPDES program. Compliance with the permit's discharge limits, with the exception of violations due to the Coal Pile Treatment Facility and the Biodenitrification Plant for which projects to improve performance are currently underway, did not present any significant problems. Overall compliance was 95.5%. There was increased activity in the areas of groundwater monitoring, hazardous waste and PCB waste management to comply with Federal regulations

Radioactivity monitoring in Ireland of air, deposition and water 1982-1987

International Nuclear Information System (INIS)

Sequeira, S.; McRandall, M.; Hayden, E.; Cunningham, J.D.

1989-02-01

The Nuclear Energy Board in conjunction with the Meteorological Service undertakes an environmental radioactivity monitoring programme with the objective of determining levels of artificially produced radioactivity in the Irish environment. The levels of radioactivity in airbourne dust, total fallout samples, precipitation and drinking water are presented for 1982, 1983, 1984, 1985, 1986 and 1987

Effluent management and pollution control

International Nuclear Information System (INIS)

Ananda Narayanan, R.; Vedamoorthy, S.

2006-01-01

Generation of waste/effluent has a direct impact on environment, the higher the generation of waste higher the environmental impact. Though complete prevention of radioactive waste generation is a difficult task, keeping the waste generation to the minimum practicable is essential objective of Radioactive Waste Management. In doing so, it is essential to minimize waste generation at all the stages of a Nuclear Plant Cycle. Waste minimization refers to both a) Waste generation by operational and maintenance activities of plant and b) Secondary waste resulting from predisposal management of Radioactive Waste. The management of the effluent can be done in efficient manner by better designs, improved procedure, periodic reviews and above all inculcate the awareness amongst the waste generators since minimisation of waste, at source is the most efficient way to safe guard the environment. Commissioning and rich operating experience of waste management plant gather novel ideas which result in beneficial improvements in the system and operating procedure. Some of the steps initiated by designers and site agencies towards this are worth mentioning. (author)

Portsmouth gaseous diffusion plant environmental monitoring report for calendar year 1975

International Nuclear Information System (INIS)

Martin, W.E.; Netzer, W.D.

1976-01-01

At the Portsmouth Gaseous Diffusion Plant the ambient atmosphere and all effluent streams are sampled and analyzed regularly for conformance to applicable environmental standards. Although neither the State of Ohio nor the federal government has established standards for fluorides in the ambient atmosphere or in vegetation, these parameters also are monitored because fluoride compounds are used extensively in the gaseous diffusion process. Radioactivity is measured in air, water, food, soil, and sediments; and radiation doses are calculated for the public. All public radiation doses are well within federal standards. Non-radioactive effluent parameters either comply with federal standards, or there are projects planned to allow compliance. A disposal facility to remove chromium from recirculating cooling water blowdown will begin operation in June 1976. Also, pH adjustment facilities for liquid effluents and electrostatic precipitators for a coal-fired steam plant are planned for the near future

Bulk monitoring and segregation of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M., E-mail: helen.beddow@nuvia.co.uk [Nuvia Limited, Harwell Oxford, Didcot, Oxfordshire (United Kingdom)

2014-07-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

Bulk monitoring and segregation of radioactive wastes

International Nuclear Information System (INIS)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M.

2014-01-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

Infrared thermography applied to monitoring of radioactive waste drums

International Nuclear Information System (INIS)

Kelmer, P.; Camarano, D.M.; Calado, F.; Phillip, B.; Viana, C.; Andrade, R.M.

2013-01-01

The use of thermography in the inspection of drums containing radioactive waste is being stimulated by the absence of physical contact. In Brazil the majority of radioactive wastes are compacted solids packed in metal drums stored temporarily for decades and requires special attention. These drums have only one qualitative indication of the radionuclides present. However, its structural condition is not followed systematically. The aim of this work is presents a methodology by applying thermography for monitoring the structural condition of drums containing radioactive waste in order to detect degraded regions of the drums. (author)

Environmental radioactive monitoring, evaluation and protection in luminous workshops of a factory

International Nuclear Information System (INIS)

Dai Hanbin; Xiang Ming; Tan Jianzu

2009-01-01

Fluorescent technique is often used to display instrumental indicator in the dark environment. Luminous workshops of a factory smear and depict the glassware by means of fluorescent power with adulterated radioactive matter. Because of adulterated radioactive matters such as 226 Ra, 40 K emit alpha-ray,beta-ray and gamma-ray, while they decay spontaneously, and high dose or cumulative radiation can damage human body in different degrees. Therefore, any radioactive damage to human body caused by over-safety dose should be prevented strictly during the working. To ensure health and safety of working staff in luminous workshop and the public, it is necessary to regularly have radioactive monitoring and evaluation to luminous workshop and its surrounding environment. Through the environment radioactive monitoring, the authors analyze its environmental radioactive level,and try to find out the possible problems so as to propose some protective measures for personal health. (authors)

Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

International Nuclear Information System (INIS)

Sharma, Ranjit; Kumar, Anoj; Vikas; Patra, R.P.; Kumar, Vikas; Singh, Rajvir; Pradeepkumar, K.S.

2012-01-01

The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that radioactive material will not reach public domain. Around the world, cases involving radioactive contamination of metallic components have occurred due to radioactive sources/contaminated metal scrap reaching the public domain. Radiological monitoring of inactive scrap material is essential as it may get into various usages in public domain where controls cannot be implemented. The method of detection is measurement of gamma dose rates due to any loose/fixed radioactive contamination in the scrap or presence of any radioactive material/source. In addition prevention of any inadvertent/malicious act leading to radioactive material reaching the public domain through scrap being essential, this monitoring gains further importance. This paper describes the methodology and experience in detection of presence of radioactivity at inactive Scrap monitoring facility. Even though radioactive sources of high strength with potential for serious environmental hazard have not been detected, few cases of contaminated material (MS plate/equipments etc with extremely low level of 137 Cs and Uranium contamination) have been detected and identified using portable gamma spectrometer. If proper monitoring is not carried out the dispersal of radioactivity to the environment can be a matter of concern due to metal scrap reaching recycling industry resulting in huge cost of decontamination and waste disposal. These events may also have negative impact on the export from the country resulting in economic losses. The impact of such events can be ruled out by effective scrap monitoring techniques which ensure that even small quantity of radioactivity escaping into public domain can be prevented. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of very low level of radioactivity

Annual report on radioactive discharges and monitoring of the environment 1991. V. 1

International Nuclear Information System (INIS)

1992-01-01

This Annual Report supplements and updates British Nuclear Fuel plc's Health and Safety and the Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical groups doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I includes, for each of the Company's sites, annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical groups doses for each site are presented in summary tables at the beginning of each chapter. (author)

Groundwater monitoring plan for the Hanford Site 200 Area Treated Effluent Disposal Facility

International Nuclear Information System (INIS)

DB Barnett

2000-01-01

Seven years of groundwater monitoring at the 200 Area Treated Effluent Disposal Facility (TEDF) have shown that the uppermost aquifer beneath the facility is unaffected by TEDF effluent. Effluent discharges have been well below permitted and expected volumes. Groundwater mounding from TEDF operations predicted by various models has not been observed, and waterlevels in TEDF wells have continued declining with the dissipation of the nearby B Pond System groundwater mound. Analytical results for constituents with enforcement limits indicate that concentrations of all these are below Practical Quantitation Limits, and some have produced no detections. Likewise, other constituents on the permit-required list have produced results that are mostly below sitewide background. Comprehensive geochemical analyses of groundwater from TEDF wells has shown that most constituents are below background levels as calculated by two Hanford Site-wide studies. Additionally, major ion proportions and anomalously low tritium activities suggest that groundwater in the aquifer beneath the TEDF has been sequestered from influences of adjoining portions of the aquifer and any discharge activities. This inference is supported by recent hydrogeologic investigations which indicate an extremely slow rate of groundwater movement beneath the TEDF. Detailed evaluation of TEDF-area hydrogeology and groundwater geochemistry indicate that additional points of compliance for groundwater monitoring would be ineffective for this facility, and would produce ambiguous results. Therefore, the current groundwater monitoring well network is retained for continued monitoring. A quarterly frequency of sampling and analysis is continued for all three TEDF wells. The constituents list is refined to include only those parameters key to discerning subtle changes in groundwater chemistry, those useful in detecting general groundwater quality changes from upgradient sources, or those retained for comparison with end

Historical radioactive waste in France: Situation and lessons learnt

International Nuclear Information System (INIS)

Blary, C.; Averous, J.

2002-01-01

Some radioactive waste, produced several decades ago, have been stored until now, awaiting an appropriate treatment process or further policy decision, in facilities that are now considered under the present safety standards. When no satisfactory improvements can be brought about the safety of the storage, the retrieval of the old radioactive waste is required. In France, typical facilities concerned with historical radioactive waste are shallow wells, pools, silos, effluents tanks and trenches. Several aspects, sometimes combined, make the retrieval usually more difficult and longer than thought. These aspects are mainly a lack of concern regarding retrieval of the waste when designing the facilities, an insufficient waste characterisation or record keeping, a lack of monitoring, this lack of monitoring becoming more detrimental as the facility is ageing, and a lack of maintenance. Problems related to historical radioactive waste management have been identified and operators are making efforts to eradicate them. Without considering the financial cost of old radioactive waste retrieval, operators have to face problems such as risk of loss of radionuclides containment, radiation protection, handling and transportation. The nuclear safety authority has decided to make safety guidelines regarding designing and operating storage facilities as a result of experience feedback from the storage operators. (author)

Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

International Nuclear Information System (INIS)

Sharma, Ranjit; Anoj Kumar; Vikas; Singh, Rajvir; Patra, R.P.; Vikas Kumar; Pradeepkumar, K.S.

2012-01-01

The paper describes about the experience gained during the radiation monitoring of inactive scrap generated at various nuclear facilities. This type surveillance is carried out to prevent the spread of radioactivity in public domain and also as requirement by regulatory authorities. The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that no radioactive material reaches public domain. This paper describes the methodology and experience in detection of radioactivity at inactive Scrap monitoring facility. Inactive scraps (metallic and non metallic) generated from various nuclear facilities of BARC, Trombay is dispatched to Trombay Village Store (TVS) for temporary storage before auction to the public. The monitoring at the facility includes visual inspection and radiation measurement before loading the scrap in the truck. An online PC based monitoring system and portable monitoring instruments in the range (nSv/h-µSv/h) are used to carry out radiation monitoring of inactive scrap loaded in a vehicle. Radioactive source of high activity with potential for serious environmental hazard has not been detected, but few cases of presence of radioactive/contaminated material (MS plate/equipments with low level of 137 Cs contamination) have been detected and identified using portable gamma spectrometer. Implementation of strict regulatory measures and radiation monitoring at nuclear facilities can minimize the probability of radioactive material reaching the public domain. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of radioactivity in scrap if any. (author)

Radioactive Liquid Waste Treatment Facility Discharges in 2011

Energy Technology Data Exchange (ETDEWEB)

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

MONITORING OF RADIOACTIVITY AT DNURT CAMPUS

Directory of Open Access Journals (Sweden)

L. F. Dolina

2016-06-01

Full Text Available Purpose. The research paper aims to determine radioactive contamination on the territory of campus of Dnipropetrovsk National University of Railway Transport named after Academician V. Lazaryan (DNURT. Methodology. The dosimeters measured the radioactive contamination in different places (points of DNURT campus, focusing on public places. The centres of measurements became dormitories, monuments, stops, main entrances of the new and the old buildings, classrooms, basements, a swimming pool, boiler room and others. Findings. The conducted radiation monitoring for the first time in the history of the University discovered the source of radioactive contamination on DNURT territory and campus. The highest radiation background is observed on three points, namely: the pedestal of the monument, the monument to students-soldiers, the main entrance of the new building (columns. This can be explained by granite materials, which the pedestals and the stairs are made of. Originality. The largest contribution to the total value of annual effective dose of human exposure is made by ionizing radiation sources (IRS of building materials (65 - 70%. The radioactivity level of building materials is determined by the content of natural radionuclides that are included in uranium-radium and thorium decay series (18 and 12 radionuclides as well as potassium-40. Radioactivity of building materials is evaluated by the content of dominant radionuclides radium-226, thorium-232 and potassium-40. Their dominant role is explained by the fact that these long-lived high-energy - emitters are the products of decay of radium-226 in uranium series of and radium-224 in thorium series, exposing radioactive gases (radon-222 and radon-220. Radioactive gases are accumulated in the basements of educational buildings; their decay is accompanied by 100% alpha radiation, which is the most dangerous. Practical value. It is necessary to set radioactivity signs near the objects with high

Radiation protection instrumentation. Monitoring equipment. Atmospheric radioactive iodine in the environment

International Nuclear Information System (INIS)

1995-01-01

This international standard applies to portable or installed equipment for the monitoring of radioactive iodine (such as I-131 or I-125) in air in the environment of nuclear installations during normal operation, during design basis events, and in emergency situations. The monitoring involves continuous sample trapping and, where adequate, automatic start of sampling. The document deals with radioactive iodine monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of changes in the air circuit. (P.A.)

Environmental monitoring at major U.S. Energy Research and Development Administration contractor sites: calendar year 1975. Volume 2

International Nuclear Information System (INIS)

1976-08-01

This report describes environmental monitoring conducted during 1975 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The environmental monitoring program consists of onsite sampling of water, gaseous, and air effluents, as well as offsite monitoring of water, air, soil, and radiation levels in the vicinity of the site. The report discusses releases of small quantities of radioactivity to the Ohio River from the Shippingport Atomic Power Station during 1975. The Beaver Valley Power Station was under construction during the report year, and therefore, made no radioactive releases. Additional analyses of the effluent from the reactor portion of Shippingport were performed to ensure that the water quality standards specified by Energy Research and Development Administration Manual Chapter 0510 and the Commonwealth of Pennsylvania have been met. The results of environmental monitoring described by this report show that Shippingport operations and the pre-operational phase of the Beaver Valley Power Station have not adversely affected the surrounding environment

Use of Portal Monitors for Detection of Technogenic Radioactive Sources in Scrap Metal

Science.gov (United States)

Solovev, D. B.; Merkusheva, A. E.

2017-11-01

The article considers the features of organization of scrap-metal primary radiation control on the specialized enterprises engaging in its deep processing and storage at using by primary technical equipment - radiation portal monitors. The issue of this direction relevance, validity of radiation control implementation with the use of radiation portal monitors, physical and organizational bases of radiation control are considered in detail. The emphasis is put on the considerable increase in the number of technogenic radioactive sources detected in scrap-metal that results in the entering into exploitation of radioactive metallic structures as different building wares. One of reasons of such increase of the number of technogenic radioactive sources getting for processing with scrap-metal is the absence of any recommendations on the radiation portal monitors exploitation. The practical division of the article offers to recommendation on tuning of the modes of work of radiation portal monitors depending on influence the weather factor thus allowing to considerably increase the percent of technogenic radioactive sources detection.

Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river

International Nuclear Information System (INIS)

Duhamel; Menoux; Candillon

1958-01-01

1) The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr 90 and Cs 137 by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr 90 is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr 90 in drinking water is 8.10 -8 c/m 3 or 4.10 -10 g/m 3 . So a percentage of 40 μg/litre of Sr is enough which is difficult to find out in loaded water, 10) Important elements

Vadose zone monitoring plan using geophysical nuclear logging for radionuclides discharged to Hanford liquid waste disposal facilities