Published June 1964 | Version v1
Miscellaneous Open

Analysis of accident caused by temperature increase at the RA reactor in Vinca

Creators

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

Description

The objective of this work was to determine the maximum time interval without accident due to mechanical failures. The following accidents caused by mechanical failures are taken into account: loss of moderator flow, moderator leaking with or without circulation, and accidents caused by removal of fuel channels from the reactor vessel. Obtained numerical and experimental results are presented. Experimental device installed at the reactor was used for verification of calculation results. The analysis was done for the most damaging conditions and thus the obtained results represent the lowest boundary values

Availability note (English)

Also available from the Institute of nuclear sciences Vinca

Abstract (Serbian)

Rad je baziran na pronalazenju maksimalnih vremena pri kojima i pored mehanickih kvarova nece doci do udesa. Posmatrani su slucajevi: prestanak cirkulacije moderatora, curenje moderatora uz i bez postojece cirkulacije, kao i udesi pri vadjenju tehnoloskih kanala iz reaktorskog suda. Dobijeni su rezultati numerickom i eksperimentalnom metodom. Eksperimentalna aparatura je postavljena da bi se dobila potvrda numerickih rezultata. U radu se vodilo racuna da se uvek analiziraju najnepovoljniji slucajevi pa su zato i dobijeni rezultati donje granice resenja (author)

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Additional details

Additional titles

Original title (Serbian)
Analiza udesa usled povisenja temperature na reaktoru RA u Vinci

Publishing Information

Imprint Place
Beograd-Vinca (Serbia)
Imprint Pagination
22 p.
Report number
INIS-CS--0052

INIS

Country of Publication
Serbia
Country of Input or Organization
Serbia
INIS RN
41124057
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT; FUEL CHANNELS; LOSS OF COOLANT; LOSS OF FLOW; MELTDOWN; R-A REACTOR; REACTIVITY INSERTIONS; REACTOR SHUTDOWN; TEMPERATURE COEFFICIENT
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SHUTDOWN; TANK TYPE REACTORS; THERMAL REACTORS

Optional Information

Notes
7 figs, 6 refs; This record replaces 37038523
Secondary number(s)
IBK--53