Zobrazeno 1 - 10
of 35
pro vyhledávání: '"K. O. Ott"'
Publikováno v:
Nuclear Technology. 124:284-290
The main-steam-line-break (MSLB) transient in a pressurized water reactor (PWR) is a core overcooling event that can result in a large positive reactivity insertion. In most analyses the shutdown margin is sufficiently large that the core does not re
Autor:
Tehsin Hamid, K. O. Ott
Publikováno v:
Nuclear Science and Engineering. 113:109-121
A study is conducted to investigate conceptual liquid-metal reactor (LMR) core concepts, employing some unconventional design features for improved economics and safety. The unconventional design elements are used to supplement the conventional measu
Autor:
K. O. Ott
Publikováno v:
Nuclear Science and Engineering. 113:122-135
A simplified model for a liquid-metal-cooled reactor (LMR) transient analysis, in which point kinetics as well as lumped descriptions of the heat transfer equations in all components are applied, is converted from a differential into an integral form
Autor:
K. O. Ott, Nasir Majid Mirza
Publikováno v:
Nuclear Science and Engineering. 110:168-176
There is a problem in the neutron flux calculation in regions with a strong spectral transition from epithermal toward thermal. Space-dependent group constants are developed for the thermal range t...
Publikováno v:
Nuclear Science and Engineering. 103:25-36
Analytical exploratory investigations indicate that transition effects such as streaming cause a considerable spatial variation in the neutron spectra across resonances; streaming leads to opposite effects in the forward and backward directions. The
Publikováno v:
Nuclear Science and Engineering. 88:1-15
The main results of several years of research on neutron and gamma-ray physics in the Purdue Fast Breeder Blanket Facility (FBBF) are summarized. Presented are neutron capture rates in /sup 238/U, /sup 232/Th, gold, tungsten, and manganese, and fissi
Publikováno v:
Nuclear Science and Engineering. 96:102-111
Fission rate measurements were performed in the Purdue Fast Breeder Blanket Facility (FBBF) and compared with two-dimensional 50-group diffusion calculations on an absolute basis. Fission rates in /sup 239/Pu, /sup 235/U, /sup 237/Np, /sup 238/U, and
Publikováno v:
Nuclear Technology. 71:341-352
Publikováno v:
Nuclear Science and Engineering. 93:262-272
Experimental and computational studies of the gamma-ray energy deposition rate in the Fast Breeder Blanket Facility (FBBF) were performed with thermoluminescent dosimeters (TLDs). Various correctio...
Publikováno v:
Nuclear Science and Engineering. 72:152-159
The time-dependent breeding of fuel in a growing system of breeder reactors can be characterized by the transitory (instantaneous) growth rate, γ(t), which expresses both fuel and reactor propertie...