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Neutron Scattering

Neutron Scattering - JuSER - Forschungszentrum Jülich

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this way even at a comparatively low average neutron flux very high pulsed fluxes may be<br />

obtained . In the thermal range for example, the Rutherford source is able to surpass the ILL<br />

with respect to the peak flux significantly . Such pulsed sources can be used in particularly<br />

well for time of flight experiments which will be discussed later in the school .<br />

2 .4 <strong>Neutron</strong> detection<br />

Generally the detection of neutrons is performed indirectly through particular nuelear<br />

reactions which produce charged particles . A number of possible reactions are listed in<br />

Table 2 .2 .<br />

Proportionality counters operate wich a gas volume of 3He or BF 3 (enriched with' °B) . Such<br />

counters deliver sensitivities to nearly 100% . Scintillation counters absorb neutrons within a<br />

polymer or glass layer which is enriched by 6 Li and ZnS . <strong>Neutron</strong> absorption then leads to<br />

fluorescence radiation which is registered via a photo multiplayer or directly wich a<br />

photographie film. Finally, fission chambers use the n + 235U reaction and have generally only<br />

a low counting probability . They are mainly used in order to control the beam stability and are<br />

applied as monitors.<br />

Table 2 .2 :<br />

Nuclear reactions used for neutron detection .<br />

The cross sections are given in barns (lb =10 -28 m 2 ).<br />

Reaction Cross Section for Particles Energy Total Energy<br />

25meV neutrons generated [MeV] [MeV]<br />

P 0.57 0 .77<br />

n + 3He 5333 b 3 T 0 .2<br />

6 n + Li<br />

941 b<br />

3T 2 .74 4 .79<br />

4He 2 .05<br />

4He 1.47 2 .30<br />

n +' °B 3838 b 7 Li 0 .83<br />

y 0.48(93%)<br />

n + 235U 681 b fission 1-2<br />

2-8

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