Distribution of fission products in Peach Bottom HTGR fuel element F03-01
Element F03-01 was a so-called high-rhodium driver element centrally located within core 2 adjacent to a ''type 2'' control rod. Although not instrumented, the element was estimated to have operated at significantly higher temperatures than the majority of the driver elements and, therefore, was expected to exhibit enhanced release and migration of fission products from the fuel into its graphite components. Because of these expectations, the examination of element F03-01 was believed to be especially important. The element received an equivalent of 897 full-power days of irradiation prior to scheduled termination of core operation. The examination procedures emphasized the determination of radionuclide distributions in the graphite portions of the fuel element. Axial gamma scans indicated 36 Ci of /sup 137/Cs in the sleeve of the element and 9.8 Ci in the spine. From similar measurements, 358 Ci of /sup 137/Cs was estimated to be in the fuel, showing that approximately 13% of it was found in the graphite components. Axial distributions also indicated that significant amounts of the total inventory of /sup 137/Cs moved toward the bottom of the element during operation. The axial distribution of /sup 134/Cs was similar to that of /sup 137/Cs. Other nuclides found in the fuel of the element included /sup 95/Zr, /sup 103/Ru, /sup 106/Ru, /sup 125/Sb, /sup 141/Ce, /sup 144/Ce, /sup 154/Eu, and /sup 233/Pa. Nuclides found in the graphite, in addition to /sup 134/Cs and /sup 137/Cs, included /sup 54/Mn, /sup 60/Co, /sup 106/Ru, /sup 110m/Ag, /sup 144/Ce, and /sup 154/Eu. Europium-154, a nuclide formed in the fuel by neutron capture in the stable fission product /sup 153/Eu, appeared to have been released from the fuel and migrated along the element to about the same extent as the two cesium isotopes. About 1 Ci of /sup 110m/Ag was found in the spine and sleeve of the element. None of the other nuclides appeared to have been significantly released from the fuel.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6806169
- Report Number(s):
- ORNL/TM-5996; TRN: 78-014256
- Country of Publication:
- United States
- Language:
- English
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FUEL ELEMENTS
HTGR TYPE REACTORS
PEACH BOTTOM-1 REACTOR
AMOEBA EFFECT
FISSION PRODUCT RELEASE
FISSION PRODUCTS
GAMMA FUEL SCANNING
GRAPHITE
METALLOGRAPHY
SPATIAL DISTRIBUTION
CARBON
DISTRIBUTION
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL SCANNING
GAMMA RADIOGRAPHY
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
INDUSTRIAL RADIOGRAPHY
ISOTOPES
MATERIALS TESTING
NONDESTRUCTIVE TESTING
NONMETALS
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated