The Concentration Of Tritium In Urine And Internal Radiation Dose Estimation Of PTNBR Radiation Workers

Journal Article · Thu Dec 23 00:00:00 EST 2010 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.3537927· OSTI ID:21511436

Tjahaja, Poppy Intan; Sukmabuana, Putu; Aisyah, Neneng Nur ^[1]

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1. PTNBR BATAN, Jl. Tamansari no. 71, Bandung 40132 (Indonesia)

The operation of Triga 2000 reactor in Nuclear Technology Center for Materials and Radiometry (PTNBR BATAN) normally produce tritium radionuclide which is the activation product of deuterium atom in reactor primary cooling water. According to previous monitoring, tritium was detected with the concentration of 8.236{+-}0.677 kBq/L and 1.704{+-}0.046 Bq/L in the primary cooling water and in reactor hall air, respectively. The tritium in reactor hall air chronically can be inhaled by the workers. In this research, tritium content in radiation workers' urine was determined to estimate the internal radiation doses received by the workers. About 50-100 mL of urine samples were collected from 48 PTNBR workers that is classified as 24 radiation workers and 24 administration staffs as a control. Urine samples of 25 mL were then prepared by active charcoal and KMnO{sub 4} addition and followed with complete distillation. The 2 mL of distillate was added with 13 mL scintillator, shaked vigorously and remained in cool and dark condition for about 24 hours. The tritium in the samples was then measured using liquid scintillation counter (LSC) for 1 hour. From the measurement results it was obtained that the tritium concentration in the urine of radiation workers were in the range of not detected and 5.191 Bq/mL, whereas in the administration staffs the concentration were between not detected and 4.607 Bq/mL. Internally radiation doses were calculated using the tritium concentration data, and it was found the averages about 0.602 {mu}Sv/year and 0.532 {mu}Sv/year for radiation workers and administration staffs, respectively. The doses received by the workers were lower than that of the permissible doses from tritium, i.e. 40 {mu}Sv/year.

• OSTI ID: 21511436
• Journal Information: AIP Conference Proceedings, Vol. 1325, Issue 1; Conference: 4. Asian physics international symposium, Bandung, West Java (Indonesia), 12-13 Oct 2010; Other Information: DOI: 10.1063/1.3537927; (c) 2010 American Institute of Physics; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
61 RADIATION PROTECTION AND DOSIMETRY
ATOMS
DEUTERIUM
DISTILLATION
FISSION
INTERNAL IRRADIATION
LIQUID SCINTILLATION DETECTORS
MANAGEMENT
NUCLEAR FUELS
OPERATION
PERSONNEL
PRIMARY COOLANT CIRCUITS
RADIATION DOSES
RADIATION SOURCES
REACTOR FUELING
TRIGA TYPE REACTORS
TRITIUM
URINE
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BIOLOGICAL MATERIALS
BIOLOGICAL WASTES
BODY FLUIDS
COOLING SYSTEMS
DOSES
ENERGY SOURCES
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FUELS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
MATERIALS
MEASURING INSTRUMENTS
NUCLEAR REACTIONS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIATION DETECTORS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SCINTILLATION COUNTERS
SEPARATION PROCESSES
SOLID HOMOGENEOUS REACTORS
STABLE ISOTOPES
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES