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Temperature behavior of 12 wt.% U TRIGA fuel

Abstract

Stainless steel clad 12 wt % U TRIGA fuel elements have been used to refuel the Penn State University's Breazeale Reactor (PSBR). When 12 wt % U fuel containing nominally 55 gms of {sup 235}U per fuel element is substituted for the 8.5 wt % U fuel containing nominally 38 gms {sup 235}U, higher fuel temperatures were produced in the 12 wt % U fuel than in the 8.5 wt % U fuel at the same reactor powers. The higher fuel temperature can be related to the higher power densities in the 12 wt % U fuel. The power density is calculated to be 35% higher in the 12 wt % U fuel when 6 of these fuel elements are substituted for 8.5 wt % U fuel in the innermost ring, the B ring. Temperatures have been calculated for the 12 wt % U fuel in the above configuration for both steady state and pulse conditions, assuming a 35% higher fuel density in the 12 wt % U fuel and the results compare favorably with the experimental measurements. This is particularly true when the comparison is made with temperature data taken after exposing the new fuel elements to a series  More>>
Authors:
Levine, S H; Geisler, G C; Totenbier, R E [1] 
  1. Pennsylvania State University (United States)
Publication Date:
Jul 01, 1974
Product Type:
Conference
Report Number:
INIS-US-09N0328; TOC-5
Resource Relation:
Conference: 3. TRIGA owners' conference, Albuquerque, NM (United States), 25-27 Feb 1974; Other Information: Country of input: International Atomic Energy Agency (IAEA); 6 refs, 6 figs; Related Information: In: 3. TRIGA owners' conference. Papers and abstracts, 432 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COMPARATIVE EVALUATIONS; CONFIGURATION; DENSITY; FUEL ELEMENTS; NUCLEAR FUELS; POWER DENSITY; PULSES; STAINLESS STEELS; STEADY-STATE CONDITIONS; URANIUM 235
OSTI ID:
21217744
Research Organizations:
General Atomic Co., San Diego, CA (United States)
Country of Origin:
United States
Language:
English
Other Identifying Numbers:
TRN: US09N0351086528
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 4.13-4.28
Announcement Date:
Oct 19, 2009

Citation Formats

Levine, S H, Geisler, G C, and Totenbier, R E. Temperature behavior of 12 wt.% U TRIGA fuel. United States: N. p., 1974. Web.
Levine, S H, Geisler, G C, & Totenbier, R E. Temperature behavior of 12 wt.% U TRIGA fuel. United States.
Levine, S H, Geisler, G C, and Totenbier, R E. 1974. "Temperature behavior of 12 wt.% U TRIGA fuel." United States.
@misc{etde_21217744,
title = {Temperature behavior of 12 wt.% U TRIGA fuel}
author = {Levine, S H, Geisler, G C, and Totenbier, R E}
abstractNote = {Stainless steel clad 12 wt % U TRIGA fuel elements have been used to refuel the Penn State University's Breazeale Reactor (PSBR). When 12 wt % U fuel containing nominally 55 gms of {sup 235}U per fuel element is substituted for the 8.5 wt % U fuel containing nominally 38 gms {sup 235}U, higher fuel temperatures were produced in the 12 wt % U fuel than in the 8.5 wt % U fuel at the same reactor powers. The higher fuel temperature can be related to the higher power densities in the 12 wt % U fuel. The power density is calculated to be 35% higher in the 12 wt % U fuel when 6 of these fuel elements are substituted for 8.5 wt % U fuel in the innermost ring, the B ring. Temperatures have been calculated for the 12 wt % U fuel in the above configuration for both steady state and pulse conditions, assuming a 35% higher fuel density in the 12 wt % U fuel and the results compare favorably with the experimental measurements. This is particularly true when the comparison is made with temperature data taken after exposing the new fuel elements to a series of pulses. These calculations and data will be presented at the meeting. (author)}
place = {United States}
year = {1974}
month = {Jul}
}