Thermal neutron flux density standard within the C.S.N. at Casaccia (in Italian)
Technical Report
·
OSTI ID:4939260
A thermal-neutron flux density standard was built with six Am --Be neutron sources using graphite and polyethylene as moderating medium. The total neutron emission rate of the sources was 14.6 x 10/sup 6/ s/sup -1/. The graphite was a cylinder 20 cm high and 25 cm in diameter, with a central cavity 10 cm high and 5 cm in diameter. The thermal neutron density in the cavity, measured by gold activation, yielded 1.220 x 10/sup 4/ cm/sup -2/ s/sup -1/ plus or minus with a cadmium ratio of 9.31 plus or minus 0.05. An independent absolute measurement of the flux made by P.T.B. in Braunschweig, Germany, gave 1.217 x 10/sup 4/ cm/sup -2/ s/sup -1/ plus or minus 0.9%. (14 figures, 2 table s) (auth)
- Research Organization:
- Comitato Nazionale per l'Energia Nucleare, Rome (Italy)
- Sponsoring Organization:
- Sponsor not identified
- NSA Number:
- NSA-29-028509
- OSTI ID:
- 4939260
- Report Number(s):
- RT/PROT--(73)37
- Country of Publication:
- Italy
- Language:
- Italian
Similar Records
Thermal neutron flux density standard at C.S.N. Casaccia: design and calibration
Use of the F-1 reactor as a standard thermal neutron field for calibration of neutron detectors
MEASUREMENT OF THE DIFFUSION PARAMETERS OF GRAPHITE
Journal Article
·
Mon Dec 31 23:00:00 EST 1973
· Energ. Nucl. (Milan), v. 21, no. 1, pp. 53-55
·
OSTI ID:4347557
Use of the F-1 reactor as a standard thermal neutron field for calibration of neutron detectors
Journal Article
·
Sun Dec 31 23:00:00 EST 1972
· Tr. Soyuznogo Nauch.-Issled. Inst. Priborostr., no. 20, pp. 11-14
·
OSTI ID:4324221
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