Transient non-boiling heat transfer in a fuel rod bundle during accidental power excursions
Creators
- 1. Technische Univ. Berlin (Germany, F.R.). Inst. fuer Kerntechnik
Description
One important aspect in analysis of the unprotected transient overpower accident is the prediction of time and location of fuel pin failure. The accuracy of such predictions decisively depends of the adequate modeling of the heat transfer processes involved. The present investigation focusses on the fundamental heat transfer aspects in the first phase of the power-excursion transient before boiling of the coolant starts, by solving the four coupled three-dimensional time-dependent energy equations for the fuel rod (fuel, gap, clad) and the coolant. The analysis surpasses similar previous studies, e.g. by Gopalakrishnan, in several important aspects. Most notable is that the geometry of the fuel rod bundle is correctly described in its three dimensions and the turbulent energy transport within the coolant is modeled more realistic and in a consistent manner over the entire Prandtl number range of interest using results from a specially tailored phenomenological turbulence model. The physical problem studied is the transient non-boiling heat transfer of a cylindrical fuel rod consisting of fuel, gap, and cladding to a steady, fully developed turbulent flow. A digital computer program has been developed, on the basis of finite-difference techniques, to solve the governing partial differential equations with their associated subsidiary conditions. (Auth.)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0 444 85062 7
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- v. D p. 4/3 1-14.
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, USA.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10430672
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIFFERENTIAL EQUATIONS; EXCURSIONS; FINITE DIFFERENCE METHOD; FORECASTING; FUEL ELEMENT CLUSTERS; FUEL ELEMENT FAILURE; FUEL RODS; HEAT TRANSFER; PRANDTL NUMBER; SIMULATION; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; TRANSIENTS; TURBULENCE
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; EQUATIONS; FUEL ASSEMBLIES; FUEL ELEMENTS; ITERATIVE METHODS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS