Published June 1990 | Version v1
Journal article

Criticality safety studies of a proposed uranium-zirconium alloy fuel fabrication facility

  • 1. Univ. of Tennessee, Knoxville (USA)

Description

The purpose of the project described in this paper is to provide criticality limits and guidance for the initial planning phase of a new facility for the production of a new metal alloy fuel material for the Hanford N reactor. The proposed fuel material composition is a uranium-zirconium alloy consisting of ∼90.7 wt% zirconium and 9.3 wt% uranium. While the anticipated enrichments range from 55 to 70 wt% 235U, this analysis considers only 100 wt% 235U for simplicity and conservatism. The fuel material would be produced in the form of a solid, as-cast double billet using an arc-melt process. Two finished billets result from one as-cast double billet. The results of these studies indicate that the proposed production facility can be operated safely as long as the proper physical constraints and administrative criticality controls are implemented

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
61
Series
Trans. Am. Nucl. Soc.
Journal Page Range
185
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
10-14 Jun 1990.
Place
Nashville, TN (USA).

Optional Information

Secondary number(s)
CONF-900608--.