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Neutrons fissions

The metal has good structural strength and a low fission neutron cross sechon, making it useful in nuclear applicahons. [Pg.72]

Kinetic energy of fission fragments Instantaneous y-rays Kinetic energy of fission neutrons Radioactive decay of fission fragments, P energy Radioactive decay of fission fragments, y energy... [Pg.429]

Schematic view of fission. Neutron capture produces a highly unstable nucleus that distorts and then splits into smaller nuclei and a few free neutrons. ... Schematic view of fission. Neutron capture produces a highly unstable nucleus that distorts and then splits into smaller nuclei and a few free neutrons. ...
What is the meaning of the terms prompt and delayed with respect to the fission neutrons ... [Pg.329]

What is the fraction of fission neutrons with energies greater than 2 MeV (in the laboratory frame) ... [Pg.329]

The current availability of small portable 14 MeV neutron generators and the future availability of high intensity 252Cf spontaneous fission neutron sources will certainly result in the wide spread use of activation techniques for non-destructive "on-stream" product analysis in industry. The cost of the required instrumentation for many types of activation analysis is not excessive, as compared to the cost of other modem analytical instrumentation. The simple off-on operation of the new sealed-tube neutron generators and minimal maintenance associated with the use of an isotopic Z5ZCf neutron source will permit operation of the analytical facility with technician-level personnel. The versatility of the activation technique justifies its inclusion among the other major analytical techniques employed in any modem analytical facility. [Pg.85]

The fission neutrons at birth have energies of approximately 1 to 2 MeV In a thermal reactor the neutron energy is rapidly reduced through collisions with light nuclei to thermal (—.02 to 1 eV), to promote for more efficient capture. Besides the nuclear fuel, there are many other materials in the reactor core also competing for the neutrons, including the moderator (the material used to slow down or thermalize the neutrons), fertile nuclides that produce additional fissile material (discussed in a later section), neutron poisons present in control rods, the coolant, fuel element cladding, and other structural materials. [Pg.950]

More complex is the production of Pu-238 (used for isotopic heat sources) and californium-252 (used in research as a source of fission neutrons). For Pu-238 there are two... [Pg.955]

The A value is inversely proportional to the fission neutron generation rate, so it significantly depends on the sought value of Keff, which we would like to determine on the basis of experimental value a and calculated values Peff and a. Thus, another formula is used ... [Pg.213]

In order to control subcriticality of SRP s storage facilities by the stationary method, it is necessary to know the induced fission neutron generation rate per gram of fuel (Qind) and the rate of neutron generation by above-mentioned sources per gram of fuel (Qsp) in the maximum neutron flux points [17], If Qsp and Qmd are known, the system multiplication can be written in the following way ... [Pg.214]

The relative error of subcriticality determination by the stationary method, AKeff/Keff is decreasing with the Keu growth. So that the value of AKeff/Keff could be equal to 1%, the required accuracy in determination of spontaneous and induced fission neutron generation rate has to be no worse than 7 % at Keff 0.9 and 1.4 % at... [Pg.215]

Fajgelj A, Horvat D, Pucelj B. 1992. Chromosome abberations induced in human lymphocytes by U-235 fission neutrons. Strahlentherapie and Onkologie 406-411. [Pg.365]

While 8 is somewhat greater than 1, both p and / are somewhat smaller than 1. Therefore, for approximate calculations, epf can be set 1. The fission factor rj varies appreciably with the energy of the neutrons, as shown in Fig. 11.4 for The neutron losses in a reactor of finite dimensions can be taken into account approximately by the sum L +1 , where Ls is the mean slowing-down length of the fission neutrons in the moderator and L the mean diffusion length in the fuel-moderator mixture. For a spherical reactor of radius R the approximate relation is... [Pg.205]


See other pages where Neutrons fissions is mentioned: [Pg.402]    [Pg.430]    [Pg.430]    [Pg.208]    [Pg.423]    [Pg.450]    [Pg.451]    [Pg.451]    [Pg.451]    [Pg.1754]    [Pg.72]    [Pg.130]    [Pg.1800]    [Pg.157]    [Pg.388]    [Pg.389]    [Pg.389]    [Pg.390]    [Pg.82]    [Pg.84]    [Pg.63]    [Pg.83]    [Pg.147]    [Pg.402]    [Pg.429]    [Pg.430]    [Pg.430]    [Pg.430]    [Pg.143]    [Pg.308]    [Pg.317]    [Pg.211]    [Pg.287]    [Pg.287]    [Pg.157]    [Pg.202]   
See also in sourсe #XX -- [ Pg.10 , Pg.11 ]




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Detection techniques fission neutrons

Fast fission neutrons

Fission Neutron Source

Fission The process of using a neutron

Fission The process of using a neutron to split

Fission by fast neutrons

Fission by thermal neutrons

Fission delayed neutrons

Fission neutron capture

Fission neutron emission

Fission neutron spectrum

Fission neutron transmutation products

Fission neutron yields

Fission neutron-induced

Fission of U-235 by Neutrons

Fission products neutron absorption

Fission-neutron irradiation, effects

High-energy fission neutrons

Neutron absorbers induced fission

Neutron capture fission product

Neutron in fission

Neutron reactions fission

Neutron reactor types, fission product

Neutrons fission and

Neutrons per fission

Neutrons produced in fission

Penetration of Fission Neutrons Through Water

Thermal neutron reactors, fission product

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