Radiation Protection Procedures Research Articles

Adsorption and volatility of free 211At and 125[formula omitted

The present study was undertaken to extend our knowledge of the behaviour of 211At in the laboratory environment. An unexpectedly high volatility of free 211At was found, up to 85% during an hour. Free 211At also adsorbed more onto the plastic material studied than 125I-. The results of this study show that it is of great importance to pay careful attention to radiation protection procedures during the practical handling of free 211At.

血管造影検査における術者の被曝線量評価と放射線防護用具による被曝低減

A study was performed to evaluate operator dose during diagnostic and interventional radiology procedures (IVR) and to establish methods of operator dose reduction with a radiation protective device. Operator dose was measured by glass dosimeters worn on the neck and on the abdomen outside the lead apron. In addition, the dose of the primary beam at the collimator surface was measured, which made it possible to define the correlation between the entrance air kerma, measured with Skin Dose Monitor, and operator dose exposed during the monitored procedure. IVR protectors were developed to decrease the amount of scatter radiation received by operators performing the procedures, and their effects were evaluated in abdominal and cardiac angiography procedures. The average effective dose and doses of the neck and abdomen outside the lead apron, estimated for individual procedures, were as follows: abdominal angiography procedures: effective dose, 0.07 mSv; neck area, 0.18 mSv; abdominal area, 0.51 mSv; cardiac angiography procedures: effective dose, 0.07 mSv; neck area, 0.13 mSv; abdominal area, 0.68 mSv. Operator doses were well correlated with exposure dose in abdominal angiography procedures (diagnostic procedure r=0.84, IVR r=0.77). It was found that 68.0% of the effective dose in abdominal angiography procedures and 43.0% of the effective dose in cardiac angiography procedures could be reduced by the use of IVR protectors. Operator and patient doses in interventional radiology were interdependent. The minimization of operator doses is particularly important during interventional radiology, and it is necessary to be aware of practical radiation protection procedures. Measures that reduce patient dose will also reduce occupational exposure. Moreover, operator dose could be substantially reduced by the use of IVR protectors in addition to wearing a protective lead apron during IVR. It was suggested that IVR protectors are effective radiation protective devices in interventional radiology procedures.

Transport of radioactive material in India

The Competent Authority for the enforcement of regulations on safe transport of radioactive material in India is the Atomic Energy Regulatory Board (AERB). Transport of radioactive material in India is governed by the AERB code which is based on the IAEA regulations on the safe transport of radioactive material (Safety Series No 6 1986). The code is being revised to take into account the revision made in the IAEA transport regulations, i.e. TS-R-1 (ST-1, revised). For a majority of the shipments, the consignor is the supplier of radioactive material to various users in medicine, industry and research. Radiation safety in the transport of these packages is ensured through a well defined regulatory framework and radiation protection procedures. The consignor is required to ensure that the packages used meet the prescribed standards. Transport documents, in addition to the consignor's declaration, include instructions to the carrier and transport emergency card (TREMCARD). TREMCARD describes the potential hazards involved in the shipment, primary emergency response action plans and emergency contact numbers. A well-defined emergency response system is in place in India to handle emergencies which may occur during transport of radioactive material. The paper highlights the volume of transport of radioactive material, package approval procedure and various aspects including the emergency response system adopted in India to ensure the safe transport of radioactive material.

Radioisotope for occult lesion localisation (ROLL) of the breast does not require extra radiation protection procedures

Aim of study: Dosimetry data from patients and hospital personnel involved in the use of radioisotope for occult lesion localisation (ROLL) of the breast were collected to determine the need for extra radiation protection procedures. Methods: Sixty-three patients have been enrolled to date into a randomised trial evaluating ROLL. Two megabecquerels of 99mTc- MAA in a syringe was mixed with X-ray contrast medium; this was injected directly into the lesion under image guidance. A gamma-detecting probe (Neo-Probe) was used to locate the area of radioactivity. Radiation doses to all staff groups were estimated using time and motion studies and dose rate measurements at a range of distances during each stage of ROLL. Results: The finger dose [FD](±95% CI) was considered to be the critical variable for surgeons and radiologists. Surgeon FD = 9.3±3.3 μSv, Radiologist FD = 0.5±0.13 μSv. Whole body doses [WBD](±95% CI) were estimated for other staff groups. Nurse WBD = 0.4±0.4 μSv, porter WBD: nil, contamination and waste: nil. Conclusions: In the case of a surgeon performing 100 procedures per annum, a FD dose of approximately 1 mSv is received, well within the annual dose limit of 150 mSv. Annual WBD to assisting staff may reach 0.04 mSv, compared to an annual limit of 6 mSv. These low doses and the lack of contamination of radioactive waste indicate that no additional radiation protection measures are required.

Sister chromatid exchanges in lymphocytes of nuclear medicine physicians

Objective: The aim of this study was to assess whether occupational exposure to chronic, low doses of Iodine 131 (I-131) and Technetium 99m (Tc-99m) may lead to genotoxicity. Medical personnel occupied in nuclear medicine departments are occupationally exposed to low doses of I-131 and Tc-99m. The determination of the frequency of sister chromatid exchanges (SCEs) and of cells with a high frequency of SCEs (HFC) is considered to be a sensitive indicator for detecting genotoxic potential of mutagenic and carcinogenic agents. Therefore, we examined peripheral lymphocytes from nuclear medicine physicians for the presence of both SCE and HFC. Methods: Sixteen exposed nuclear medicine physicians (non-smokers) were compared to 16 physicians (non-smokers) who had not been exposed to chemical or physical mutagens in their usual working environment at the same hospital. Results: A statistically significant difference was found between SCE frequencies and HFC percentages measured in lymphocytes from the exposed and control groups. Conclusions: The present observation on the effect of chronic low doses of I-131 and Tc-99m indicates the possibility of genotoxic implications of this type of occupational exposure. Hence, the personnel who work in nuclear medicine departments should carefully apply the radiation protection procedures and should minimize, as low as possible, radiation exposure to avoid possible genotoxic effects.

Decommissioning of the Astra research reactor: Review and status on July 2003

The paper describes work on the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Organizational, planning, and dismantling work done until July 2003 including radiation protection and waste management procedures as well as the current status of the project are presented. Completion of the decommissioning activities is planned for 2006.

Future of radionuclide therapy

Despite much research over the last few decades, there still remains considerable uncertainty as to the genetic impact of ionizing radiation on human populations, particularly at low levels. The aim of the present study was to provide data on the genetic hazards due to occupational exposure of low doses of ionizing radiation in nuclear medicine departments. The assessment of primary DNA damage in peripheral blood leukocytes of medical staff was performed using the alkaline comet assay and the data obtained were compared with the results of conventional cytogenetic biodosimetry using the chromosome aberration (CA) test. Altogether 120 subjects (60 exposed and 60 controls) participated in the study. Statistically significant increases in primary DNA damage and increased frequencies of CAs compared to controls were observed. Within the exposed population, significant inter-individual differences in DNA damage were found, indicating differences in genome sensitivity. Age and gender were not confounding factors, while smoking enhanced the levels of primary DNA damage only in control subjects, as revealed by both biomarkers studied. The present study suggests that genotoxic damage results from exposure to chronic low doses of ionizing radiation in nuclear medicine departments. Therefore, the exposed medical personnel should carefully comply with the radiation protection procedures and should minimize radiation exposure where possible to avoid potential genotoxic effects. The results obtained in this study point to the significance of biological indicators providing information on the actual risk to the radiation exposed individuals. According to our results, the alkaline comet assay and CA test are sensitive biomarkers that can be used as additional complements to physical dosimetry for assessing exposure to radiation in nuclear medicine personnel.

Radioguided surgery of breast cancer: radiation protection survey.

The aim of this study was to estimate the radioactive risk for surgical staff performing radioguided sentinel lymph node (SN) biopsy and to calculate the contamination level in the operating room for assessment of the possible need for specific radiation protection procedures. We studied 20 patients who were selected for quadrantectomy and SN biopsy. The day before surgery a volume of 0.15 mL of 99mTc-nanocoll was injected: the activity was 3.11 +/- 0.85 MBq in group A (15 pts) and 11.6 +/- 0.6 MBq in group B (5 pts). External radiation to staff was evaluated by measuring the exposure rate in air one hour after radiopharmaceutical administration. The air KERMA rate during surgery was estimated considering the physical decay of 99mTc. Contamination of disposable materials and surgical instruments in the operating room was measured using a contamination monitor, whereas the residual activity in the SN and the injection site was measured with a gamma probe. The exposure rate at 20 cm from the injection site was 0.75 microSv/h when the most radioactive patients (group B) were treated. Contamination in the operating room proved to be negligible. Considering the number of radioguided treatments carried out by a surgeon in one year, an equivalent effective dose of 0.075 mSv was estimated; the recommended dose limit according to the relevant Italian law, DL 230/95, is 1 mSv/yr. Surgical staff therefore do not require a classification of "exposed workers" and there is no need to supply the operating room with special containers for radioactive waste.

Radiation produced by the LEP superconducting RF cavities

The LEP superconducting RF cavities present an important radiation source both during the conditioning and during normal working conditions. Before their installation in the accelerator the cavities are tested and conditioned in a laboratory bunker up to their maximum achievable field, which in some cases can be as high as 9 MV m −1. This paper discusses radiation measurements carried out on both single cavities and standard 4-cavity modules. Following a brief description of the processes underlying the emission of radiation, the results of photon and neutron measurements are given. The induced radioactivity in various materials is also evaluated; shielding guidelines and radiation protection procedures are briefly discussed.

THE TOTAL MANAGEMENT OF NORM IN THE OFFSHORE PETROLEUM INDUSTRY

Naturally Occurring Radioactive Materials (NORMs) in the offshore petroleum industry are generally associated with the formation of scale in pipes and vessels. As scale and sludge contain radioactive isotopes of radium they are in the category of Low Specific Activity (LSA) NORMs. Handling of NORMs creates issues involving occupational health and safety, environmental protection and radioactive waste management and waste disposal. Barium(Radium)Sulfate scale is highly insoluble and can create serious production problems by clogging pipes and valves.The paper discusses the external gamma radiation monitoring at the external surfaces of well and oil production pipes which assists in establishing the scale thickness patterns in pipes and in identifying the optimum location of a scale inhibitor injection point.To minimise radiation doses received by workers special NORM handling Work Procedures and Instructions supported by radiation protection training need to be developed. If facility personnel are trained in radiation protection and Work Procedures and Instructions are adopted it is possible to effectively manage personal radiation exposures below the public limit of 1 millisievert per year. Under such conditions no personal radiation monitoring during routine operations is required and the assessment of routine annual external radiation doses may be carried out through yearly external gamma radiation surveys of of fshore petroleum production facilities.The NORM waste cannot be disposed of onshore within the same disposal sites used for general non-radioactive waste. In Australia only the NORM waste generated in Western Australia can be disposed of onshore in an official low level radioactive waste disposal facility. It is important that Governments of other States and Territories address the onshore NORM waste disposal option. Regulations should also address a screening method for scrap metal contaminated by NORMs to be released for smelting.

Radiation protection design philosophy for a door interlock system for shared room remote afterloading brachytherapy.

A single remote afterloading system can sometimes be used for the radiation treatment of two or more patients in separate rooms simultaneously. This configuration poses certain radiation protection problems, especially in a busy clinic where some of the treatment rooms have to be used for other non-radiation related patients even though not all radiation treatments have been completed. In this report we describe a door interlock system that has been designed to allow for radiation protection purposes during radiation treatment but is disabled when the radiation treatment is completed--with enough safeguard built in to prevent accidental bypass of the interlock. In addition, the quality control procedures of the radiation monitor devices for these treatment rooms are described. These radiation protection procedures could be generalized to other remote afterloading systems.

Medical and organizational aspects related to the Goiânia accident

On 13 September 1987, a severe radiation accident occurred in the city of Goiânia in central Brazil. Approximately 250 people were directly affected by the radiation, receiving slight to very severe external, partial or whole body, irradiation, and presenting internal and external contamination. Fourteen patients developed some degree of marrow failure, eight developed the clinical signs and symptoms of acute radiation syndrome (ARS), and four eventually died of ARS complications. Twenty-eight people showed acute localized radiation injuries ranging from first to third degree. The author describes the circumstances of the event, the first-aid measures taken on the site, and the medical structure organized to triage and treat the casualties. Aspects relating to hospital contamination control, radiation protection and decontamination procedures are also discussed.

Medical and Related Aspects of the Goiania Accident

On 13 September 1987, a radiation accident occurred in the city of Goiânia in Central Brazil. Approximately 250 people were exposed to a 137Cs source from an abandoned radiotherapy unit. At least 14 patients showed some degree of bone marrow depression, and eight developed the classical signs and symptoms of acute radiation syndrome (ARS). Twenty-eight people presented local radiation injuries ranging from first to third degree, and 104 individuals showed evidence of internal contamination. This paper describes the circumstances of the event, the first-aid measures taken, the criteria adopted for triage of the exposed population, and the radiation protection procedures used during the clinical management of the irradiated individuals.

Radiation protection during treatment of children with 131I-meta-iodobenzylguanidine.

This paper describes the radiation protection procedures that were used in caring for three children treated with therapeutic amounts of 131I-meta-iodobenzylguanidine. Since it was not possible to leave a child alone in a shielded room for several days, the presence of one parent was requested during the treatment. The dose equivalent to the parent was kept to an acceptable level of approximately 1 mSv. This dose equivalent was almost completely due to external radiation since blocking of the parent's thyroid led to a negligible dose equivalent from internal contamination.

Three Mile Island experience and its influence on radiation protection procedures

Three Mile Island experience and its influence on radiation protection procedures

A design to minimize exposure to scattered X‐ray radiation

AbstractA design is described which conforms to OSHA recommendations for good radiation protection procedures. This design can be used on most units where X‐ray optics are exposed to the atmosphere. It proves sufficient and should make most nonvacuum X‐ray units comply with today's recommended dosage levels. A survey of our instrument gave results well below the maximum permissible level of 2.5 milliröntgen per hour for scattered radiation at a distance five centimeters from the housing surface. The detected scattered radiation was in the range of 0.03 milliröntgen per hour, which is within the limits of normal background radiation.

Inservice Education in Radiation Health

Attention is called to the responsibility of all institutions where ionizing radiation is used, even infrequently. Agencies must accept the challenge of radiation protection and provide a well organized, well planned, and well executed program of inservice education. Personnel who fully understand the significance of radiological health are willing and eager to establish good radiation protection procedures for themselves and others.

A radiologist looks at radiation protection procedures: L. H. Garland. Radiology 82: 963, June, 1964

A radiologist looks at radiation protection procedures: L. H. Garland. Radiology 82: 963, June, 1964

A RADIOLOGIST LOOKS AT RADIATION PROTECTION PROCEDURES.

Forebear to judge, for we are sinners all. Close up his eyes and draw the curtain close; And let us all to meditation.—King Henry VI, Part II, Act 3. The first thing we do, let's kill all the lawyers.—Ibid, Act. 4. Periodic meditation on radiological protection procedures is desirable for many reasons, not least because they tend to be accompanied by a plethora of overtones emotional and a pallor of facts scientific. So meditate we shall, both as physician and as citizen. And lawyers will not be killed, because they are necessary, especially in the construction of sensible regulations! Radiation protection procedures in this essay will be considered primarily from the point of view of the patient undergoing x-ray examination. The persons actually using radiation equipment should have enough knowledge of its hazards to protect themselves and their staffs from harm in so far as present information permits…even if they do not always so possess. While physicians and dentists are principally responsible for hu...