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Transistorized Pulse Counting Equipment
This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date:
July 26, 1960
Creator:
Henry, John J.
System:
The UNT Digital Library
Reactor Physics Calculations for the Msre
A compilation is presented of results obtained to date from a number of reactor physics calculations for the molten salt reactor experiment (MSRE). Included are one-dimensional multigroup and two-dimensional twogroup calculations of critical mass, flux, and power density distributions; gamma heating in the core can, reactor vessel, and core support grid; drain tank criticality; and an estimate of the beta , gamma , and delayed neutron dose rates due to fission products in the fuel contained in the pump bowl. For a cylindrical core 54 in. in diameter and 66 in. high, graphite-mcderated with 8 vol% fuel salt, the calculated critical loading is 0.76 mole% uranium (93.3% U/sup 235/), which is equivalent to a critical mass of 16 kg. At a reactor power of 10 mw, the peak power density in the core assuming a homogeneous mixure of fuel salt and graphite is 10 watts/cm/sup 3/, the average power density is 4 watts/cm/sup 3/. The computed peak thermal flux is 7.3 x 10/sup 13/ neutrons/cm/sup 2/ sec and the average is 2.5 x l0/sup 13/ neutrons/cm/sup 2/ sec. Gamma heating prcduces a power density of 0.2 watts/cm/sup 3/ in the core wall at the midplane and 0.4 watts/cm/sup 3/ in …
Date:
July 26, 1960
Creator:
Nestor, Jr, C. W.
System:
The UNT Digital Library
Criticality in the Hrt Transfer Vessel
None
Date:
July 26, 1960
Creator:
Jaye, S. & Bennett, L. L.
System:
The UNT Digital Library
FLUORINE DISPOSAL USING CHARCOAL
Wood, coke, and coconut-shell charcoals were evaluated for fluorine entrapment. The coconut-shell charcoal produced the smallest amount of solid and liquid reaction products. Efficient removal of fluorine was accomplished by the coconut-shell charcoal in a 5-in.-diameter reactor with a feed containing 25% fluorine at flow rates from 100 to 400 scfh and reactor-wall temperatures of 1200 to 1800 deg F. (C.J.G.)
Date:
July 26, 1960
Creator:
Houston, N. W.
System:
The UNT Digital Library