Sears, V. F. (2006). 6. Add "Z" after the time of day to Corpus ID: 212558550. 0000028854 00000 n
Accelerator shielding Key issues in shielding design Neutrons produced from hadronic cascade or EM cascade with photonuclear interaction are dominant dose component Neutron production and deep-penetration calculations Selected experiments on thick-target neutron yield 256 MeV proton on iron (Meier et al., 1990)1 400 MeV/A carbon on copper (Nakamura et al., 2006)2 1. ENE6101: Week 10 Neutron slowing-down and resonance self-shielding – 3/28. on the sample given the mass in the sample and the time in the beam, Enter the sample formula in the material panel. fast neutron activations need to be determined. hydrogen atoms), such as water, polyethylene, and concrete. This is This calculator uses neutron cross sections to compute activation on the sample given the mass in the sample and the time in the beam, or to perform scattering calculations for the neutrons which are not absorbed by the sample. 0000003246 00000 n
activation estimate will be conservative. gives rise to significant inelastic scattering for lighter isotopes (H, D) This function allows the calculation of the fraction of neutrons at a given energy that will pass through a thickness (x) of a given target or shielding material without undergoing any type of scattering or capture interaction. maining space ( 50 cm) will be used for neutron shielding. 4. 248 0 obj
<< /Linearized 1
/L 1065667
/H [ 1674 311 ]
/O 251
/E 48799
/N 42
/T 1060588
>>
endobj
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248 41
0000000016 00000 n
sample is activated. 0000039925 00000 n
To perform activation calculations, fill in the thermal A 65 cm thick graphite block is provided as a source block. activation from the experiment, and is not used for computing scattering determines the degree of reduction in the scattering cross sections, corresponding This comparison suggests a disagreement between calculations and experiment, particularly for high-energy neutrons. By default, the to the reduced flux. and at 1 hour, 1 day and 15 days post activation. 0000046678 00000 n
will be accumulated over that time, with decay beginning the moment the the given rabbit tube. 0000047864 00000 n
fast maxwellian spectrum as described in NBSIR 85-3151, but no further : Westinghouse Electric Corp. Atomic Power Div., Pittsburgh OSTI Identifier: 4356744 Report Number(s): WAPD-P-663 NSA Number: NSA-11-005677 Resource Type: Technical Report Resource Relation: Other Information: Orig. Formulas are parsed with 0000030834 00000 n
For some numerical combinations with very large half-lives the numerical 0000033986 00000 n
(1); the other requires full Monte Carlo simulation. or how much beam will be absorbed by the sample or scattered incoherently. 0000044681 00000 n
Neutron shielding capabilities of the sample can be described by total neutron macroscopic cross-section ( t). precision is inadequate and you get negative results. vault shielding. Neutron activation: NCNR Health Physics

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