Accession Number : AD0265903

Title :   ANPP NUCLEATE BOILING PROGRAM. LABORATORY SIMULATION OF PM-1 CORE THERMAL AND HYDRUALIC TRANSIENT CONDITIONS

Corporate Author : MARTIN CO BALTIMORE MD

Personal Author(s) : JICHA,J.J. ; LIGHTNER,R.

Report Date : OCT 1961

Pagination or Media Count : 1

Abstract : A system was developed for the simulation of reactor power excursions due to unchecked control rod withdrawal and for loss of pumping power incidents as experienced by a fuel element and its flow channels. The PM-1 pressurized water reactor plant was used. It was shown that the system could simulate power excursions having varying rates of rise and peak power. The system could als be programmed to give various rates of flow decay accompanied by power decays caused by rod scram or reactor void and temperature coefficients. Experiments were performed with a test section which was designed to simulate the thermal and hydraulic characteristics of a selected PM-1 reactor fuel element. The element selected for simulation was that considered most susceptible to burnout. An analog study was performed to specify behavior during credible PM-1 incidents of unchecked control rod withdrawal and loss of pumping power. (Author)

Descriptors :   REACTOR POWER DENSITY

Distribution Statement : APPROVED FOR PUBLIC RELEASE