Flux Perturbations by Thermal Neutron Detectors

Autor: Richard K. Osborn, G. Ronald Dalton
Rok vydání: 1961
Předmět:
Zdroj: Nuclear Science and Engineering. 9:198-210
ISSN: 1943-748X
0029-5639
DOI: 10.13182/nse61-a15604
Popis: The transport equation that describes the thermal neutron population in and around a neutron detector was converted to an iterative integral equation. This irtegral equation was then solved for a wide range of specific cases using a digital computer. Using this method of calculation, the effects upon neutron density of nonisotropic scatter in the surrounding medium, of finite detector dimensions, and of scatter by the detector were calculated to an accuracy of better than I%. Detailed maps of the scalar neutron density in and around finite detectors were available from the calculations. The problem of nonisotropic, non- uniform initial neutron density was formulated using the integral method. (auth)
Databáze: OpenAIRE