Accession Number : ADA268704


Title :   Reactivity Estimation and Validation for the Control of Reactor Neutronic Power


Descriptive Note : Master's thesis.,


Corporate Author : MASSACHUSETTS INST OF TECH CAMBRIDGE DEPT OF ELECTRICAL ENGINEERING


Personal Author(s) : Lasota, Charles S


Full Text : https://apps.dtic.mil/dtic/tr/fulltext/u2/a268704.pdf


Report Date : May 1993


Pagination or Media Count : 265


Abstract : From July 1986 to July 1991, a joint MIT-SNL research team developed a controller capable of safely raising reactor power by approximately five orders of magnitude in a few seconds. This controller was experimentally demonstrated on the MIT Research Reactor (MITR-II) as well as on the 'Sandia National Laboratories' Annular Core Research Reactor (ACRR). This controller's intended application is for the control of spacecraft nuclear reactors. However, it also has direct application for the control of military, commercial, and research reactors. This report is concerned with a method for enhancing the controller's performance through the development of an improved model to validate estimates of the magnitude of reactivity feedback effects. The focus is on the Doppler effect but the resulting model is applicable to other types of reactivity feedback such as that associated with the thermal effects of a hydrogen coolant.


Descriptors :   *VALIDATION , *REACTIVITIES , *NUCLEAR REACTORS , *NEUTRONS , *POWER , *REACTOR OPERATION , THERMAL PROPERTIES , CONTROL , MODELS , ESTIMATES , FEEDBACK , DOPPLER EFFECT , COOLANTS , ADAPTIVE SYSTEMS , FORTRAN , HYDROGEN , THESES , SPACECRAFT , DETECTORS


Subject Categories : Nuclear Power Plants and Fission Reactor Eng
      Fission Reactor Physics
      Nuclear Physics & Elementary Particle Physics


Distribution Statement : APPROVED FOR PUBLIC RELEASE