Published 1989 | Version v1
Miscellaneous Metadata-only

Experiments to determine the thermal-mechanical response when molten Zircaloy-4 flows onto a ballooned pressure tube

Creators

  • 1. Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
  • 2. Ontario Hydro, Toronto, ON (Canada)

Description

An experimental program has been set up to investigate the thermal-mechanical behaviour of a fuel channel when molten Zircaloy-4 (Zr-4) from a fuel bundle flows onto a ballooned pressure tube. The first two tests of the series were carried out with a pressure of 3 MPa inside the pressure tube and subcooling on the calandria tube of about 20 degrees celsius. Results show that the calandria tube dries out directly under the Zr-4 melt but quickly rewets within 22 s. The maximum calandria tube temperature measured directly under the molten Zr-4 droplet was 900 degrees celsius. This paper describes the experimental setup and summarizes results from these first two tests. (author). 4 refs., 1 tab., 8 figs

Part of:
Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3

Additional details

Publishing Information

ISBN
0-919307-39-6; 0-919784-17-8
Imprint Title
Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3
Imprint Pagination
3 v. [1200 p.].
Journal Page Range
v. 2 p. 9.26-9.30.
ISSN
0706-1293; 0227-1907
Report number
INIS-mf--14668

Conference

Title
10. annual conference of the Canadian Nuclear Society.
Dates
4-7 Jun 1989.
Place
Ottawa, ON (Canada).

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
27015066
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CALANDRIAS; FUEL CANS; FUEL CHANNELS; HEAT TRANSFER; M CODES; MECHANICAL PROPERTIES; PRESSURE TUBE REACTORS; THERMAL DEGRADATION; THERMOCOUPLES; ZIRCALOY 4
Descriptors DEC
ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; COMPUTER CODES; CONTAINERS; CORROSION RESISTANT ALLOYS; ENERGY TRANSFER; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; MATERIALS; MEASURING INSTRUMENTS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information