- Autor(in)
- Referenz
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10 Iee, T.; Seki, Y.; Iida, H.: Effects of Neutrons Streaming Through Injector Ports on Neutronics Characteristics of Fusion Reactor Proc. Second TopL, Mtg. Technology of Controlled Nuclear Fusion, Conf. 760935-P2, p. 395 (1976).
11 Santore, R. T.; Lillie, R. A.; Alsmiller, R. G.; Barnes, J. M.: Two and Three Dimensional Neutronics Calculations For the TFTR Neutral Beam Injectors. ORNL/TM-6354, Oak Ridge National Lab. (1978).
12 Sayed Ahmed, F. M.: Ann. Phys. (Leipzig) 45 (1988) 117.
13 Raso, D. J.: Monte Carlo Calculations on the Reflection and Transmission of Scattered Gamma Radiation Technical Operations, Inc., Report To-B61-39 (Revised) (1961).
14 Raso, D. J.: Nucl. Sci. Eng., 17 (1963) 411.
15 Haggmark, L. G.; Jones, T. H.; Scofield, N. E.; Gurney, W. J.: Differential Dose-Rate Measurements of Backscattered Gamma Rays from Concrete. Aluminium and Steel 23 (1965) 138 - 149.
1 Blizard, E. P.; Abbot, L. S.: Reactor Hand Book, Volume III part B, Shielding Interscience Publishers, 1962, Chap 12.
2 Marshal, J. D.: Monte Carlo Calculations and Experimental Data for Radiation Streaming Through Bent Ducts. Transactions of the American Nuclear Society Vol. 7, No. 2, Nov. 1964.
3 Cain, V. R.: Calculations of Thermal Neutron Flux Distributions in Concrete Walled Ducts Using the Albedo Model with Monte Carlo Techniques ORNL-3507, 1964.
4 Paratte, J. M.; Etemad, A.: Neutron Flux Measurements in Bent Air Ducts Through Water Paper Presented to the 5the Meeting of European-American Committee on Reactor Physics Madesimo (Italy), Jan. 1965. (Swiss Fedral Institute for Reactor Research (EIR), Wurenlingen.
5 Wade, E.; Clabiborne, H. Clyde: Methods for Calculating Effects of Ducts, Access Ways and Hales in Radiation Shields, ORNL-BSIC-20, (DASA - 1892-1) (Jan. 1968).
6 Sayed Ahmed, F. M.: The Effect of Cylindrical Air Filled Ducts in Water on the Distribution of Thermal Neutrons from a Collimated Beam. Thesis for the Degree of Master of Science (Sept. 1968).
7 Sayed Ahmed, F. M.: An Investigation of the Effects of Ducts and Voids Upon Neutron Transmission in Shield. Thesis for the Degree of Doctor of Philosophy in Science (August 1972).
8 Mahmoud Abdel Razek, M. M.: Fast Neutron Flux Distribution in Solid and Ducted Ordinary Concrete. Thesis Submitted for the Degree of Master of Science (1968).
9 Megahid, R. M.; Makarious, A. S.; El-Kolaly, M. A.: J. Phys. 12 (1981) 1.
- Seitenbereich
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0491 - 0497
- Zusammenfsg.
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<B>Untersuchungen zur Rückwärtsstreuung thermischer Neutronen an Strahldurchführungen in Betonabschirmungen</B>
Die räumliche Rückwärtsstreuung thermischer Neutronen an Strahlungs-durchführungen in Beton wird experimentell untersucht. Die Neutronenflußverteilung wurde am Ende des Durchlasses und senkrecht zu seiner Achse mit einem Indiumthermaldetektor gemessen. Die experimentelle Technik wird beschrieben, und die Resultate für verschiedene Durchlaßdurchmesser graphisch dargestellt und analysiert.
Experimental studies on the angular flux distributions of backscattered thermal neutrons by neutral beam injector ducts (NBID) in ilmenite concrete are performed. The neutron flux distributions have been measured at the end of the ducted assembly and perpendicular to the duct axis by means of Indium thermal detector. The experimental facility and the detector activity measurement techniques are described. Results concerning injector ducts with different diameters are graphically represented. Calculations to analyse the experimental results are given.
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