Published December 1997 | Version v1
Miscellaneous Open

Report of the Technology Service - Annex B

  • 1. Vinca Institute of Nuclear Sciences, Beograd (Serbia)

Description

This annex covers: description of the organisational structure of the service, safeguard activities, dosimetry and radiation protection tasks and an overview of the the activities of this Service. During 1997, there have been 12 safeguard IAEA inspections. Each time inspection covered fresh fuel, every third inspection included control of the spent fuel storage pool, and once during the fuel inventory control the reactor core was included. The objective of inspecting the fuel element from the core was to control visually the depositions on the fuel element surface. It was found that deposits exist on the surface of the fuel elements but they are not significant. It was mentioned that the IAEA inspectors would demand control of hot cells. Radioactivity control of the spent fuel storage pool was done by Cd-Tl detector. Analysis of the conditions in the spent fuel storage pools was one of the priority tasks during 1997. In July removal of the sludge from the bottom of the storage pool was started. Due to difficulties with the appropriate equipment it will be impossible to fulfill the scheduled plan. This annex contains a table with annual exposure doses for the reactor personnel

Abstract (Serbian)

Ova prilog sadrzi opis organizacije tehnoloske sluzbe, 'safeguard' aktivnosti, tehnicke zastite od zracenja i dozimetrije, ako i pregled svih poslova Sluzbe. Tokom 1997 bilo je 12 'safeguard' IAEA inspekcija. Tokom svake inspekcije kontrolisano je sveze gorivo, svaka treca je ukljucila kontrolu bazena za odlezavanje ozracenog goriva, a jednom je kontrolisano i jezgro reaktora RA radi vizuelne inspekcije naslaga na povrsini gorivnih elemenata. Kontrolom goriva iz jezgra utvrdjeno je da naslage postoje ali su neznatne. Negovesteno je da ce MAAE ubuduce vrsiti i kontrolu vrucih celija. Verifikacija goriva u ceholima u bazenima za odlezavanje isluzenog goriva vrsena je CD-Tl detektorom. Analiza stanja isluzenog goriva smestenog u bazene za odlezavanje bio je prioritetni posao tokom 1997. godine. U julu je odluceno da se pocne sa uklanjanjem mulja sa dna bazena i da se izvede sopstvenim sredstvima, Medjutim, planirani rokovi za izvrsenje ovih zadataka ne mogu se ispostovati usled poteskoce sa neadekvatnom opremom. vaj prilog sadrzi i pregled doza kojima je bilo izlozeno osoblje reaktora RA

Files

41123910.pdf

Files (280.8 kB)

Name Size Download all
md5:296924d7613d51331aa6777a0bd9cd73
280.8 kB Preview Download
Part of:
Research nuclear reactor RA - Annual Report 1997

Additional details

Additional titles

Original title (Serbian)
Prilog B - Izvestaj o radu tehnoloske sluzbe

Publishing Information

Imprint Place
Beograd-Vinca (Serbia)
Imprint Title
Research nuclear reactor RA - Annual Report 1997
Imprint Pagination
203 p.
Journal Page Range
6 p.
Report number
INIS-CS--0030

Optional Information

Notes
2 tabs; This record replaces 37021918 Imprint:Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu
Secondary number(s)
RA--103/R1/P2/21/03