Published January 1986 | Version v1
Journal article Metadata-only

Some transient characteristics of PIUS

Creators

  • 1. Japan Atomic Energy Res. Inst., Dept. of Reactor Safety Analysis, Tokai, Ibaraki 319-11

Description

Transient characteristics of a process inherent ultimate safety (PIUS) reactor in typical accidental situations are investigated by using the plant dynamics analysis code THYDE-W. First, the modeling and steady-state adjustment for thermal hydraulics of a PIUS is described. Then the transient calculations are made for a pump coastdown, a steam generator feedwater trip, a flow blockage, and a boron dilution. They show that inherent safety of PIUS is ensured without control rod scram. The entrance of pool water to the primary loop, however, could give rise to a potential problem of thermal shock

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
72
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
vp.
ISSN
0029-5450
CODEN
NUTYB

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17069292
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BORON; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; DILUTION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; LOSS OF FLOW; PWR TYPE REACTORS; REACTOR SAFETY; STEADY-STATE CONDITIONS; STEAM GENERATORS; THERMAL SHOCK; THERMODYNAMICS; TRANSIENTS; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; BOILERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SEMIMETALS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER MODERATED REACTORS