Published 1990 | Version v1
Miscellaneous Open

An analysis of hollow geometry reactor fuel element in transient conditions

Creators

  • 1. Institute of Nuclear Sciences Boris Kidric VINCA, Belgrade (Yugoslavia)

Description

The paper presents a proposed mathematical model of hollow geometry fuel element transient analysis. In derivating the unsteady conduction discretization equation, definition is made of some mean temperature over the time step with a weighted factor that takes the inertia of the temperature field into account. The developed numerical scheme provides stable and fast converging solutions. Finally, the paper gives fuel element thermal analysis of a hypothetical Large break LOCA in the hot leg of a primary system of RA research reactor. (author)

Availability note (English)

Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCA

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Additional details

Additional titles

Original title (Serbian)
Ponasanje supljeg reaktorskog gorivnog elementa u akcidentalnim uslovima

Publishing Information

Publisher
Society for Electronics,Telecommunications, Computers, Automation, and Nuclear Engineering
Imprint Place
Belgrade (Yugoslavia)
ISBN
86-80509-01-9
Imprint Pagination
8 p.
Report number
INIS-RS--0487

Conference

Title
34. Conference - ETAN Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering
Original Conference Title
ETAN '90: 34. Konferencija za elektroniku, telekomunikacije, racunarstvo, automatiku i nuklearnu tehniku
Dates
4-8 Jun 1990
Place
Zagreb (Yugoslavia)

INIS

Country of Publication
Yugoslavia
Country of Input or Organization
Serbia
INIS RN
38039563
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FOURIER HEAT EQUATION; FRACTURE MECHANICS; FUEL CANS; HEAT FLUX; HEAT TRANSFER; HOLLOW FUEL RODS; LOSS OF COOLANT; MATHEMATICAL MODELS; POWER GENERATION; PRIMARY COOLANT CIRCUITS; R-A REACTOR; STEAM LINES; STRESS ANALYSIS; THERMAL ANALYSIS; THERMAL CONDUCTION; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID FLOW; FUEL ELEMENTS; FUEL RODS; HEAT TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; PIPELINES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS

Optional Information

Notes
5 refs.; 5 figs., This record replaces record 22047340