Hybrid Monte Carlo/Deterministic Methods for Radiation Shielding Problems.

Monte Carlo;Radiation Transport;Shielding;Contributon;Hybrid;Nuclear Engineering and Radiological Sciences;Engineering;Nuclear Engineering & Radiological Sciences

Becker, Troy L.Martin, William R. ;

University of Michigan

关键词: Monte Carlo;    Radiation Transport;    Shielding;    Contributon;    Hybrid;    Nuclear Engineering and Radiological Sciences;    Engineering;    Nuclear Engineering & Radiological Sciences;   

Others  :  https://deepblue.lib.umich.edu/bitstream/handle/2027.42/64655/beckertr_1.pdf?sequence=1&isAllowed=y

瑞士|英语

来源: The Illinois Digital Environment for Access to Learning and Scholarship

【 摘 要 】

For the past few decades, the most common type of deep-penetration (shielding)problem simulated using Monte Carlo methods has been the source-detector problem,in which a response is calculated at a single location in space. Traditionally,the nonanalog Monte Carlo methods used to solve these problems have requiredsignificant user input to generate and sufficiently optimize the biasing parametersnecessary to obtain a statistically reliable solution. It has been demonstrated thatthis laborious task can be replaced by automated processes that rely on a deterministicadjoint solution to set the biasing parameters – the so-called hybrid methods.The increase in computational power over recent years has also led to interest inobtaining the solution in a region of space much larger than a point detector. In thisthesis, we propose two methods for solving problems ranging from source-detectorproblems to more global calculations – weight windows and the Transform approach.These techniques employ some of the same biasing elements that have been usedpreviously; however, the fundamental difference is that here the biasing techniquesare used as elements of a comprehensive tool set to distribute Monte Carlo particlesin a user-specified way. The weight window achieves the user-specified Monte Carloparticle distribution by imposing a particular weight window on the system, withoutaltering the particle physics. The Transform approach introduces a transforminto the neutron transport equation, which results in a complete modification of theparticle physics to produce the user-specified Monte Carlo distribution.These methods are tested in a three-dimensional multigroup Monte Carlo code.For a basic shielding problem and a more realistic one, these methods adequatelysolved source-detector problems and more global calculations. Furthermore, theyconfirmed that theoretical Monte Carlo particle distributions correspond to the simulatedones, implying that these methods can be used to achieve user-specified MonteCarlo distributions. Overall, the Transform approach performed more efficientlythan the weight window methods, but it performed much more efficiently for source-detectorproblems than for global problems.