Published 1979 | Version v1
Book

Thermal and structural analysis of the support region of an LMFBR reactor vessel

  • 1. General Electric Co., Sunnyvale, CA (USA). Advanced Reactor Systems Dept.

Description

The stainless steel reactor vessel of a Pool-Type LMFBR is suspended from an extension of the carbon steel deck structure through a bimetallic weld. Maximum deck temperature is 1250F (520C) while the temperature of the vessel at the sodium level is about 7000F (3710C). The thermal stresses resulting from this temperature difference, for various assumptions of vessel thermal insulation characteristics, were investigated. Steady-state vessel temperature distributions were calculated for several assumed values of the thermal insulation conductivities. The shape of the outside vessel insulation was varied to achieve an approximately linear temperature gradient in the vessel. Other conditions investigated included the effect of natural convection cooling in the top 3 feet (0.9 m) section of the vessel, and complete removal of the outside vessel insulation. The effect of raising the sodium level above the nominal 3 feet (0.9 m) and attaching the vessel at a lower elevation was also investigated. Calculated thermal stresses were combined with primary stresses resulting from deadweight and operating basis earthquake seismic loads. Results show that the proposed reactor support design appears feasible from a thermal and structural point of view. (orig.)

Additional details

Publishing Information

Publisher
North-Holland Publishing Co.
Imprint Place
Amsterdam, Netherlands
ISBN
0444-85363-4
Imprint Title
Structural mechanics in reactor technology. Transactions. Vol. G
Journal Page Range
p. G10/6 (1-8).

Conference

Title
5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
Dates
9 - 21 Aug 1979.
Place
Berlin, Germany, F.R.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
12589143
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LMFBR TYPE REACTORS; MECHANICAL STRUCTURES; MECHANICS; SUPPORTS; THERMAL ANALYSIS
Descriptors DEC
BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS

Optional Information

Secondary number(s)
INKA-Conf--79-321-277.