DIFFUSION PARAMETERS OF THERMAL NEUTRONS IN HEAVY WATER (thesis)
Technical Report
·
OSTI ID:4030363
The diffusion parameters of thermal neutrons in heavy water were determined from a 1-Mev accelerator by measuring the decay of the leakage from the finite cylinder. A 26-channel time analyzer was used for measuring the leakage. Buckling was varied from 0.062 to 0.104 cm/sup -2/. The diffusion coefficient obtained was 1.97 plus or minus 0.07 x 10/sup -5/ cm/sup 2// sec. The diffusion cooling coefficient was 4.8 plus or minus 1.1 x 10/sup -5/ cm/sup 4//sec. These values agree with those previously reported by investigators using other methods. (N.W.R.)
- Research Organization:
- North Carolina State Coll., Raleigh
- NSA Number:
- NSA-15-024264
- OSTI ID:
- 4030363
- Report Number(s):
- AD-253576
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
THE DIFFUSION PARAMETERS OF HEAVY WATER
MEASUREMENT OF THE DIFFUSION PARAMETERS OF GRAPHITE
Measurement of Diffusion Parameters and of Anisotropy of Graphite with a Pulsed Source of Neutrons; MESURE DES PARAMETRES DE DIFFUSION ET DE L'ANISOTROPIE DU GRAPHITE A L'AIDE D'UNE SOURCE PULSEE DE NEUTRONS
Journal Article
·
Tue Oct 01 00:00:00 EDT 1963
· Nuclear Science and Engineering (U.S.)
·
OSTI ID:4162529
MEASUREMENT OF THE DIFFUSION PARAMETERS OF GRAPHITE
Journal Article
·
Tue Oct 01 00:00:00 EDT 1963
· J. Nucl. Energy, Pt. A ; B
·
OSTI ID:4162532
Measurement of Diffusion Parameters and of Anisotropy of Graphite with a Pulsed Source of Neutrons; MESURE DES PARAMETRES DE DIFFUSION ET DE L'ANISOTROPIE DU GRAPHITE A L'AIDE D'UNE SOURCE PULSEE DE NEUTRONS
Technical Report
·
Mon Dec 31 23:00:00 EST 1962
·
OSTI ID:4167040