Analysis of MH-1A Loss of Coolant Accident

Abstract

Analyses of a postulated loss of coolant accident (LOCA) for the MH- 1A Nuclear Power Plant are presented for large and intermediate size breaks in the primary system. Methods and assumptions consistent with AEC Interim Acceptance Criteria were used in evaluating the performance of the Emergency Core Cooling System (ECCS). The computer codes RELAP-3 for reactor system blowdown and THETAl-B for fuel element heatup were used to perform these calculations at a core power of 49.5 MW(t). The results of the core temperature transient for various break conditions are presented and the required cooling capability of a system meeting the AEC interim criteria is discussed.

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Document Details

Document Type
Technical Report
Publication Date
Nov 09, 1972
Accession Number
AD0759118

Entities

People

  • George Johnson
  • Henry C. Gignilliat
  • James D. Franson
  • Paul M. Terpolilli

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Check Valves
  • Chemical Reactions
  • Computer Programs
  • Computers
  • Coolant Pumps
  • Energy Transfer
  • Engineering
  • Heat Capacity
  • Heat Energy
  • Heat Transfer
  • Heat Transfer Coefficients
  • High Temperature
  • Reactor Coolants
  • Reactor Kinetics
  • Thermal Conductivity
  • Three Dimensional
  • Two Dimensional

Fields of Study

  • Physics

Readers

  • Combustion and Flow Dynamics.
  • Nuclear and Radiation Engineering.
  • Systems Analysis and Design