عنوان

Modeling Neutron Interaction Inside a 2D Reactor Using Monte Carlo Method

Number

TLpq2382627953

.Language of Text, Soundtrack etc

انگلیسی

Title Proper

Modeling Neutron Interaction Inside a 2D Reactor Using Monte Carlo Method

General Material Designation

[Thesis]

First Statement of Responsibility

Islam, A. S. M. Fakhrul

Subsequent Statement of Responsibility

Scopatz, Anthony

Name of Publisher, Distributor, etc.

University of South Carolina

Date of Publication, Distribution, etc.

2019

Specific Material Designation and Extent of Item

77

Dissertation or thesis details and type of degree

M.S.

Body granting the degree

University of South Carolina

Text preceding or following the note

2019

Text of Note

Scientists and engineers have been working for many years to develop accurate approaches to analyzing nuclear power reactors using computer codes that closely model the behavior of neutrons in a reactor core. The Monte Carlo simulation method is capable of treating complex geometries with a high level of resolution and fidelity to model neutron interactions inside a reactor core. With the requirement of accurate modeling in reactor physics and dynamics and great innovation of computer technology, Monte Carlo method is becoming an ever more powerful tool and receiving rising attention. In this study, Monte Carlo method is used to model nuclear interactions between randomly moving neutrons and the fuel material, cladding material and moderator. The code, QualifyingMC, written using Python language develops the neutron diffusion scenario in a two-dimensional cartesian geometry. To evaluate the performance and accuracy of the simulation, the calculated values of the effective multiplication factor (keff), a key component in characterizing the breeding property of a fission-reactor system, was compared with reference values calculated with other codes using the same geometry, materials and boundary conditions. A good agreement within a few percent on multiplication factors was obtained. The neutron flux distribution, another important parameter in a fission-reactor system, as a function of neutron energy is also calculated and compared with the Watt distribution function. A reasonable agreement between QualifyingMC and the reference results was obtained.

Nuclear engineering

Islam, A. S. M. Fakhrul

Scopatz, Anthony

Electronic name

p

[Thesis]

276903

a

Y