How Accurately can we Calculate Thermal Systems?

Cullen, D ; Blomquist, R N ; Dean, C ; Heinrichs, D ; Kalugin, M A ; Lee, M ; Lee, Y ; MacFarlan, R ; Nagaya, Y ; Trkov, A

Lawrence Livermore National Laboratory

关键词: Uranium;    Thermal Neutrons;    Scattering;    Neutron Transport;    22 General Studies Of Nuclear Reactors;   

DOI  :  10.2172/15009834
RP-ID  :  UCRL-TR-203892
RP-ID  :  W-7405-ENG-48
RP-ID  :  15009834

美国|英语

来源: UNT Digital Library

【 摘 要 】

I would like to determine how accurately a variety of neutron transport code packages (code and cross section libraries) can calculate simple integral parameters, such as K{sub eff}, for systems that are sensitive to thermal neutron scattering. Since we will only consider theoretical systems, we cannot really determine absolute accuracy compared to any real system. Therefore rather than accuracy, it would be more precise to say that I would like to determine the spread in answers that we obtain from a variety of code packages. This spread should serve as an excellent indicator of how accurately we can really model and calculate such systems today. Hopefully, eventually this will lead to improvements in both our codes and the thermal scattering models that they use in the future. In order to accomplish this I propose a number of extremely simple systems that involve thermal neutron scattering that can be easily modeled and calculated by a variety of neutron transport codes. These are theoretical systems designed to emphasize the effects of thermal scattering, since that is what we are interested in studying. I have attempted to keep these systems very simple, and yet at the same time they include most, if not all, of the important thermal scattering effects encountered in a large, water-moderated, uranium fueled thermal system, i.e., our typical thermal reactors.