Accession Number:

AD0676687

Title:

MH-1A MAXIMUM HYPOTHETICAL ACCIDENT ANALYSIS.

Descriptive Note:

Final rept.,

Corporate Author:

ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV

Personal Author(s):

Report Date:

1968-09-01

Pagination or Media Count:

66.0

Abstract:

The Maximum Hypothetical Accident for the MH-1A nuclear reactor has been reanalyzed. The variation with time of the containment vessel temperature and pressure has been obtained. The model used is intentionally conservative. Following a double-end shear in one of the primary system pipes, the entire quantity of primary system fluid is instantaneously exposed to the containment vessel free volume and thermal equilibrium is attained among the primary fluid saturated water-steam and containment vessel air. The temperature and pressure of the containment vessel atmosphere then change with time according to the contribution of various heat sources and sinks. The effects of the containment vessel liner and internal components, fission product decay heat, metal-water reaction, hydrogen recombination, emergency core cooling systems, and pressure suppression spray systems are taken into account. Regarding the metal-water reaction, 100 of the cladding is assumed to react with steam. The evolved hydrogen is assumed to burn in place as it is generated. The peak pressure of 138 psia occurs immediately after the rupture and is within the design pressure of 155 psia. The peak atmosphere temperature of 340F also occurs immediately after the rupture. It is shown that this temperature does not impair the integrity of the containment vessel or its penetrations nor induce any unsafe malfunctions in the engineered safeguards systems. Author

Subject Categories:

  • Nuclear Power Plants and Fission Reactor Engineering
  • Nuclear Fission Reactors (Power)

Distribution Statement:

APPROVED FOR PUBLIC RELEASE