Accession Number:

AD0730929

Title:

SM-1 Core III Thermal Hydraulic Analysis,

Descriptive Note:

Corporate Author:

ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV

Report Date:

1971-09-14

Pagination or Media Count:

102.0

Abstract:

A brief description of the SM-1 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 SM-1 Core III during steady-state operation. This includes calculation of peak centerline fuel temperatures at various powers, minimum DNBR, and maximum hot channel enthalpy rise. Also included are analyses of transient conditions accompanying uncontrolled rod withdrawal in the power range and during source level startup, secondary system steam line rupture, and loss of reactor coolant flow. Author

Subject Categories:

  • Nuclear Power Plants and Fission Reactor Engineering
  • Fission Reactor Materials

Distribution Statement:

APPROVED FOR PUBLIC RELEASE