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Bioassay method for Uranium in urine by Delay Neutron counting; Metoda Bioassay Uranium dalam urin dengan pencacahan Netron Kasip

Abstract

A bioassay method for uranium in urine by neutron counting has been studied. The aim of this research is to obtain a bioassay method for uranium in urine which is used for the determination of internal dose of radiation workers. The bioassay was applied to the artificially uranium contaminated urine. The weight of the contaminant was varied. The uranium in the urine was irradiated in the Kartini reactor core, through pneumatic system. The delayed neutron was counted by BF3 neutron counter. Recovery of the bioassay was between 69.8-88.8 %, standard deviation was less than 10 % and the minimum detection was 0.387 {mu}g.
Authors:
Suratman,; Purwanto,; Sukarman-Aminjoyo, [1] 
  1. Yogyakarta Nuclear Research Centre, National Atomic Energy Agency, Yogyakarta (Indonesia)
Publication Date:
Apr 15, 1996
Product Type:
Conference
Report Number:
INIS-ID-036
Resource Relation:
Conference: Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology, Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan Teknologi Nuklir, Yogyakarta (Indonesia), 23-25 Apr 1996; Other Information: 8 refs; 2 tabs; 1 fig; Related Information: In: Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Scientific and Technology Part II : Nuclear Chemistry; Process Technology and Radioactive Waste Management; Environment, by Sudjatmoko; Karmanto, Eko Edy; Endang-Supartini [Yogyakarta Nuclear Research Centre, National Atomic Energy Agency, Yogyakarta (Indonesia)], 394 pages.
Subject:
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; BIOASSAY; CONTAMINATION; COUNTING TECHNIQUES; DELAYED NEUTRONS; IRRADIATION; NEUTRON DETECTION; RADIATION DOSES; REACTOR CORES; URANIUM; URINE
OSTI ID:
20951900
Research Organizations:
National Atomic Energy Agency, Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia)
Country of Origin:
Indonesia
Language:
Indonesian
Other Identifying Numbers:
Other: ISSN 0216-3128; TRN: ID0700051102145
Availability:
Available from INIS in electronic form; Also available from Centre for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); http://digilib.batan.go.id/prosiding/ppny961/ppny961051.pdf
Submitting Site:
INIS
Size:
page(s) 309-315
Announcement Date:
Dec 21, 2007

Citation Formats

Suratman,, Purwanto,, and Sukarman-Aminjoyo,. Bioassay method for Uranium in urine by Delay Neutron counting; Metoda Bioassay Uranium dalam urin dengan pencacahan Netron Kasip. Indonesia: N. p., 1996. Web.
Suratman,, Purwanto,, & Sukarman-Aminjoyo,. Bioassay method for Uranium in urine by Delay Neutron counting; Metoda Bioassay Uranium dalam urin dengan pencacahan Netron Kasip. Indonesia.
Suratman,, Purwanto,, and Sukarman-Aminjoyo,. 1996. "Bioassay method for Uranium in urine by Delay Neutron counting; Metoda Bioassay Uranium dalam urin dengan pencacahan Netron Kasip." Indonesia.
@misc{etde_20951900,
title = {Bioassay method for Uranium in urine by Delay Neutron counting; Metoda Bioassay Uranium dalam urin dengan pencacahan Netron Kasip}
author = {Suratman,, Purwanto,, and Sukarman-Aminjoyo,}
abstractNote = {A bioassay method for uranium in urine by neutron counting has been studied. The aim of this research is to obtain a bioassay method for uranium in urine which is used for the determination of internal dose of radiation workers. The bioassay was applied to the artificially uranium contaminated urine. The weight of the contaminant was varied. The uranium in the urine was irradiated in the Kartini reactor core, through pneumatic system. The delayed neutron was counted by BF3 neutron counter. Recovery of the bioassay was between 69.8-88.8 %, standard deviation was less than 10 % and the minimum detection was 0.387 {mu}g.}
place = {Indonesia}
year = {1996}
month = {Apr}
}