Abstract
The characterization of the neutron environment in a reusable facility for irradiation of metal-lurgical specimens, located at the Ford Nuclear reactor in Michigan, was performed with a combination of transport calculations, extensive dosimeter measurements, and neutron spectrum adjustment. The average difference between the calculated and "measured" reaction rates was ∼7 % (the calculations underpredicted the measurements), and the average absolute difference was ∼10 %. Therefore, the calculations and measurements agreed very well. The flexible facility performed excellently during several years of operation but was discontinued when the Ford reactor ceased operation. The heavy-section steel irradiation (HSSI) program is taking the initial steps toward selecting a site for a new irradiation facility, similar to the one described here.
Original language | English |
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Journal | Journal of ASTM International |
Volume | 3 |
Issue number | 7 |
DOIs | |
State | Published - 2006 |
Keywords
- Dosimetry
- Embrittlement
- Neutron irradiation
- TORT