Published 1983 | Version v1
Book

Two-dimensional steady-state thermal and hydraulic analysis code for prediction of detailed temperature fields around distorted fuel pin in LMFBR assembly: SPOTBOW

Creators

  • 1. NAIG Nuclear Research Lab., Nippon Atomic Industry Group Co., Ltd., 4-1 Ukishima-Cho Kawasaki-Ku, Kawasaki-Shi, Kanagawa-Ken 210

Description

SPOTBOW computer program has been developed for predicting detailed temperature and turbulent flow velocity fields around distorted fuel pins in LMFBR fuel assemblies, in which pin to pin and pin to wrapper tube contacts may occur. The present study started from the requirement of reactor core designers to evaluate local hot spot temperature due to the wire contact effect and the pin bowing effect on cladding temperature distribution. This code calculates for both unbaffled and wire-wrapped pin bundles. The Galerkin method and iterative procedure were used to solve the basic equations which govern the local heat and momentum transfer in turbulent fluid flow around the distorted pins. Comparisons have been made with cladding temperatures measured in normal and distorted pin bundle mockups to check the validity of this code. Predicted peak temperatures in the vicinity of wire contact point were somewhat higher than the measured values, and the shape of the peaks agreed well with measurement. The changes of cladding temperature due to the decrease of gap width between bowing pin and adjacent pin were predicted well

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-89448-110-X
Imprint Title
Thermal hydraulics of nuclear reactors
Journal Page Range
p. 1355-1364.

Conference

Title
2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
Dates
11-13 Jan 1983.
Place
Santa Barbara, CA (USA).