Simulation Calculation Study Of Gamma Radioactive Detection Of Nuclear Waste

With the development of applications in the nuclear industry, nuclear waste is aninevitable accompaniment in its development, is very important for the measurementof the radioactive nuclear waste. Radioactive waste is not only related to thecontemporary people’s safety, but also affected but the health of future generations,also have an impact on the environment. In this paper, by using the MCNP method,with the gamma ray radiation from nuclear waste as the object, analyzes the followingproblems:(1) With the point source and volume source as the research object, research theenergy spectra of gamma ray, analysis the energy spectrum, Obtain the energy of thepoint source gamma rays, gamma ray energy spectrum peak value, peak area and soon, and the simulation volume source of radioactive, Study the Gamma ray rule ofthe volume source, provide the basis for the detection of gamma rays;(2) Analysis of energy deposition, using MCNP simulation different sources ofthe gamma ray, analysis and calculation of air kerma and muscle absorbed dose;(3) Using MCNP simulation the performance radiation of shielding materials,simulate different material, analysis and calculation of the attenuation coefficient.Firstly, several MCNP model are set up, then use MCNP simulation, Finallyconcluded, the specific see below:(1) Distance from137Cs point source for the30-500cm case. mode MCNPsimulation The spectrum of137Cs, the simulation results show, under the differentdistance, energy spectrum is almost the same, In the50-500cm range, with theincrease of distance, the137Cs peak decreases, at the same time, with the increase ofdistance, Peak area is in reducing, but the amplitude is smaller;(2) Distance from60CO point source of30-500cm cases. MCNP simulationresults show, under the condition of different distance,60CO energy spectrum isalmost the same, and there are two characteristic peaks. At a distance of50-500cm,two peak values of60CO decreased with the increase of the distance, while at the sametime, as the distance increases, the peak area of two peaks are decreased, but thedecreasing amplitude is very small; (3) MCNP simulation uranium waste,results show, At1.764MeV、1.403MeV、1.378MeV、1.238MeV、1.120MeV、0.769MeV and0.609MeV, the energy peaksis obvious, and at0.609MeV, the photoelectric peak is maximum;(4) MCNP simulation objects containing thorium, At0.960MeV、0.908MeV、0.338MeV、0.129MeV、2.620MeV、0.583MeV and0.511MeV, the energy peaksis obvious, With the decay of thorium, and at0.129MeV, the photoelectric peak ismaximum;(5) Taking137Cs as the radiation source object, MCNP simulation kerma andabsorbed dose in diffrernt distance10cm,30cm,50cm,70cm and90cm,thesimulation results show, at a distance of10-30cm cases, kerma and absorbed dosedecrease sharply, in the range of30-90cm, small amplitude kerma and absorbentdecreased;(6) On several materials, MCNP simulation the radiation properties of materialsunder the condition of different energy, the simulation results show that: under thesame energy case, different thickness of the same material has the same linearattenuation coefficient,linear attenuation coefficient has a relationship with atomicnumber Z, the density of the material and component; in the energy range of0.02-1MeV, the linear attenuation coefficient of several kinds of materials isdecreased with the increase of energy.