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Titlebook: Reactor Dosimetry; Dosimetry Methods fo J. P. Genthon,H. R?ttger Book 1985 Springer Science+Business Media Dordrecht 1985 amyotrophic later

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樓主: finesse
11#
發(fā)表于 2025-3-23 12:57:02 | 只看該作者
The Effect of Damage Rates and Different Kinds of Irradiation on the Ductility of Amorphous Fe40Ni40tudied both as a function of the damage type as caused either by thermal or by fast neutrons, and of the damage rate. While the damage rate has no influence, the type of irradiation strongly influences the damage level at which the ductility of amorphous Fe.Ni.B. completely restored.
12#
發(fā)表于 2025-3-23 16:23:55 | 只看該作者
13#
發(fā)表于 2025-3-23 19:54:11 | 只看該作者
The Use of the Silicon Transistors as Damage Monitors in Reactor Neutron Metrologyse in fast neutron metrology. A general purpose n-p-n bipolar transistor (PN2222A) was chosen as the radiation damage monitor, and the change in inverse d. c. current gain before and after irradiation was chosen as the damage parameter for the measurements. A controlled annealing cycle after retriev
14#
發(fā)表于 2025-3-23 23:06:18 | 只看該作者
15#
發(fā)表于 2025-3-24 04:46:52 | 只看該作者
16#
發(fā)表于 2025-3-24 07:41:36 | 只看該作者
Neutron and Gamma Ray Flux Calculations for the Venus PWR Engineering Mockupt is the first mockup to correctly represent the heterogeneities which exist in the PWR core peripheral fuel assemblies, core baffle, core barrel, and neutron pad. This is accomplished by using a representative PWR fuel assembly geometry (15 x 15) and full thickness Type 304 stainless steel reactor
17#
發(fā)表于 2025-3-24 11:55:38 | 只看該作者
Characterization of Fuel Distribution in the Three Mile Island Unit 2 (TMI-2) Reactor System by Neutreactor core region and primary cooling system. The fuel content of TMI-2 makeup and purification Demineralizer A has been quantified with Si(Li) continuous gamma-ray spectrometry and solid-state track recorder (SSTR) neutron dosimetry. Results obtained from these gamma- ray and neutron dosimetry ex
18#
發(fā)表于 2025-3-24 16:56:26 | 只看該作者
A Study of the Embrittlement of Reactor Vessel Steel Supportsts. The shift in the nil-ductility transition temperature (ΔNDTT) at the supports has been estimated directly with the calculated fluence levels in accordance with ASTM Standard E706. Values of the displacement per atom unit (dpa) are also provided as an alternate estimate of the ΔNDTT..The results
19#
發(fā)表于 2025-3-24 19:48:02 | 只看該作者
Evaluation of Neutron Exposure Conditions for the Buffalo Reactorprovide a basis for correlation of calculated neutron exposure values with the experimental measurements. The dosimetry irradiation was performed in a mockup of an actual metallurgical assembly, which was carefully measured to ensure correct dimensions would be used in the calculation. The calculati
20#
發(fā)表于 2025-3-24 23:11:44 | 只看該作者
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