Sökning: "MCNP"

Visar resultat 1 - 5 av 13 uppsatser innehållade ordet MCNP.

  1. 1. Development of a computational method for determining gamma energy escape from calorimeters at CLAB

    Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysik

    Författare :Amela Mehic; [2022]
    Nyckelord :Nuclear physics; Calorimeter; SNF; MCNP; Dose rate; CLAB; Gamma energy; Fuel assembly; Form function; Attenuation coefficient; Gamma spectroscopy;

    Sammanfattning : Swedish Nuclear Fuel and Waste Management Company- SKB has conducted measurement campaigns at the Swedish central interim storage facility for spent nuclear fuel- CLAB over the years, extending from year 2003 to 2019 where the gamma energy escape was acquired. At CLAB the spent nuclear fuel assembly is inserted into the calorimeter; device intended to measure temperature increase due to decay heat from the fuel assembly. LÄS MER

  2. 2. Theoretical design of an XRF system for environmental measurements of Mercury in fiber banks

    Master-uppsats, Mittuniversitetet/Institutionen för elektronikkonstruktion

    Författare :Runpeng Yu; [2020]
    Nyckelord :XRF detection system; MCNP modelling; Mercury; Fiber bank;

    Sammanfattning : This thesis demonstrates the advantages of using the Energy-dispersive X-ray fluorescence (ED-XRF) system to quantify the mercury content in fiber banks at first. The Monte Carlo N-Particle (MCNP) code was then used to simulate the XRF system model with suitable parameters such as the input X-ray energy level, the detector material, and the environmental factor (water depth). LÄS MER

  3. 3. Simulations of a back scatter time of flight neutron spectrometer for the purpose of concept testing at the NESSA facility.

    Master-uppsats, Uppsala universitet/Tillämpad kärnfysik

    Författare :Benjamin Eriksson; [2018]
    Nyckelord :fusion; JET; Geant4; NESSA; NESSA facility; back scatter tof; tof; time of flight; spectrometer; neutron; ITER; Monte Carlo; simulation;

    Sammanfattning : A back scatter time of flight neutron spectrometer consisting of two scintillation detectors is simulated in Geant4 to examine whether it is possible to perform a proof of concept test at the NESSA facility at Uppsala University. An efficiency of ε = 2.45 · 10^-6 is shown to be large enough for a neutron generator intensity of 1. LÄS MER

  4. 4. Monte Carlo modelling of an X-ray fluorescence detection system by the MCNP code

    Master-uppsats, Mittuniversitetet/Avdelningen för elektronikkonstruktion

    Författare :Xiaolei Xia; [2018]
    Nyckelord :MCNP; Monte Carlo modelling; XRF detection system;

    Sammanfattning : This survey has shown, using the Monte Carlo N-Particle(MCNP) code to model a detection system, to demonstrate that it is possible to design a system to measure hazard elements in polluted water. At first, the measurement method needs to be determined. LÄS MER

  5. 5. Simulation of neutron generator assisted gamma emission tomography for inspection of fissile content in spent nuclear fuel

    Magister-uppsats, Uppsala universitet/Tillämpad kärnfysik

    Författare :Erik Wickman; [2017]
    Nyckelord :;

    Sammanfattning : This is a feasibility study of a new measurement technique for spent nuclear fuel. The technique combines gamma emission tomography with neutron activation analysis. The idea is to measure high-energy characteristic gamma from short-lived fission products and thereby verify the fissile material content in spent nuclear fuel assemblies. LÄS MER