Published 1974 | Version v1
Report Restricted

Increasing TRIGA fuel lifetime with 12 wt.% U TRIGA fuel

  • 1. Pennsylvania State University (United States)

Description

In-core fuel management studies have been performed for the Penn State Breazeale Reactor (PSBR) wherein 12 wt % U fuel elements are used to replace the standard 8.5 wt % U TRIGA fuel. The core configuration used to develop a calculational model was a 90-element hexagonal array, which is representative of the PSBR core, and consists of five hexagonal rings surrounding a central thimble containing water. The technique employed for refueling the core fully loaded with 8.5 wt % U fuel involves replacing 8.5 wt % U fuel with 12 wt % U fuel using an in-out reloading scheme. A batch reload consists of 6 new 12 wt % U fuel elements. Placing the 12 wt % U fuel in the B ring produces fuel temperatures (∼450 oC) that are well below the 800oC maximum limitation when the PSBR is operating at its maximum allowed power of 1 Megawatt. The advantages of using new 12 wt % U fuel to replace the burned up 8.5 wt % U fuel in the B ring over refueling strictly with 8.5 wt % U-Zr TRIGA fuel are clearly delineated in Table 1 where cost calculations used the General Atomic pre-1972 prices for TRIGA fuel, i.e., $1500 and $1650 for an 8.5 and 12 wt % U fuel element, respectively. Experimental results obtained to date utilizing the 12 wt % U fuel elements agree with the computed results. (author)

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Part of:
3. TRIGA owners' conference. Papers and abstracts

Additional details

Publishing Information

Imprint Title
3. TRIGA owners' conference. Papers and abstracts
Imprint Pagination
432 p.
Journal Page Range
p. 2.50-2.68
Report number
INIS-US--09N0328

Conference

Title
3. TRIGA owners' conference
Dates
25-27 Feb 1974
Place
Albuquerque, NM (United States)

Optional Information

Notes
6 refs, 7 figs, 3 tabs
Secondary number(s)
TOC--5