Accession Number : AD0726014
Title : MH-1A Core 3 Thermal Hydraulic Design Analysis.
Descriptive Note : Final rept.,
Corporate Author : ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV
Personal Author(s) : Gignilliat,Henry C. ; Langley,J. Randolph ; Neuman,Richard R.
Report Date : 01 MAR 1971
Pagination or Media Count : 116
Abstract : A brief description of the MH-1A Floating Nuclear Power Plant is given, followed by the safety system setpoints and operating limits of the reactor. The safety criteria which form the basis for safe operation and protection of the core are presented. A parametric analysis is made of the thermal-hydraulic capabilities of the MH-1A Core 3 during steady-state operation. This includes calculation of peak centerline fuel temperatures at various powers, the maximum linear heat rate, DNBR, and maximum hot channel enthalpy rise. Also included are analyses of transient conditions accompanying level startup, secondary system steam line rupture, and loss of reactor coolant flow. (Author)
Descriptors : (*REACTOR CORES, PERFORMANCE(ENGINEERING)), ELECTRIC POWER PRODUCTION, NUCLEAR REACTORS, REACTOR OPERATION, REACTOR FUEL ELEMENTS, REACTOR COOLANTS, THERMAL PROPERTIES, ENTHALPY, CONTROL RODS
Subject Categories : Nuclear Power Plants and Fission Reactor Eng
Fission Reactor Materials
Distribution Statement : APPROVED FOR PUBLIC RELEASE