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Measurements of Delayed Neutron Yields from Thermal Neutron Induced Fission of 235U, 233U, 239Pu, and 237Np

Measurements of Delayed Neutron Yields from Thermal Neutron Induced Fission of 235U, 233U, 239Pu, and 237Np PDF Author: S. B. Borzakov
Publisher:
ISBN:
Category :
Languages : en
Pages : 16

Book Description


Measurements of Delayed Neutron Yields from Thermal Neutron Induced Fission of 235U, 233U, 239Pu, and 237Np

Measurements of Delayed Neutron Yields from Thermal Neutron Induced Fission of 235U, 233U, 239Pu, and 237Np PDF Author: S. B. Borzakov
Publisher:
ISBN:
Category :
Languages : en
Pages : 16

Book Description


Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations

Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations PDF Author: Kern, Kilian
Publisher: KIT Scientific Publishing
ISBN: 3731508435
Category : Delayed neutrons
Languages : en
Pages : 254

Book Description


Grande exposition de photographies à l'occasion du 800ème anniversaire de Tramelan

Grande exposition de photographies à l'occasion du 800ème anniversaire de Tramelan PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 12

Book Description


Measurements of Delayed Neutron Parameters for U-235 and Np-237

Measurements of Delayed Neutron Parameters for U-235 and Np-237 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 134

Book Description
Delayed neutrons are emitted by excited nuclei formed in beta decay of fission products called delayed neutron precursors. About 1% of the total neutrons released in fission are delayed neutrons; however, this small fraction plays an important role in nuclear reactor control. The delayed neutrons determine the time-dependent behavior of reactors, and knowledge of parameters used to predict neutron emission rate is essential for establishing reactivity worths. The delayed neutron yields, decay constants, and the absolute yield for the six-group delayed neutrons have been measured for U-235 and Np-237. This experiment has been called for in the forecast of experiments needed to support operations in the US. The bare U-235 metal assembly Godiva IV at the Los Alamos Critical Experiment Facility (LACEF) provided the source of neutrons. Godiva IV generated about 107 total fissions in the samples for the infinite and instantaneous irradiation needed to accentuate the shorter and longer-lived groups of delayed neutrons. The detection system used in the experiment consisted of 20 He-3 tubes embedded in a polyethylene cylinder. The delayed neutron activity resulting from the fast neutron-induced fission has been measured. The measured absolute yield for U-235 was determined to be 0.0163 " 0.009 neutrons/fission. This value compares very well with the well-established Keepin absolute yield of 0.0165 " 0.0005. The newly measured absolute yield value for Np-237 was 0.0126 " 0.0007, which compares well to the recently reported value of 0.0129 " 0.0004 by Saleh and Parish. The measured values for U-235 are corroborated with period (e-folding time) versus reactivity calculations.

ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 600

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 544

Book Description


Measurement of Delayed Neutron Yields in Plutonium, Uranium-233, Uranium-238, and Thorium Relative to Yield in Uranium-235

Measurement of Delayed Neutron Yields in Plutonium, Uranium-233, Uranium-238, and Thorium Relative to Yield in Uranium-235 PDF Author: G. S. Brunson
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 32

Book Description
Delayed neutron studies have been made in the Experimental Breeder Reactor (EBR), using a conventional sample transfer system and a neutron counter comprised of BF3 tubes in a graphite geometry. Samples of U-235, U-233, U-238, Pu, and Th were irradiated in a fast flux; samples of U-235, U-233, and Pu were irradiated in a thermal flux.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 612

Book Description


ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 588

Book Description


ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 676

Book Description