Published 1991 | Version v1
Book

Loss of residual heat removal during PWR mid-loop operation

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

Loss of residual heat removal (RHR) during a mid-loop operation, i.e., operation of RHR with the primary inventory partially drained after reactor shut-down, has occurred in several PWR plants. The primary causes were a loss-of-AC power or air binding of the RHR pump. Some of these events resulted in boiling of the reactor vessel inventory and suggested the possibility that the coolant inventory would boil away to uncover the core, for a prolonged event. In JAERI, experiments simulating loss-of-RHR events were conducted at the ROSA-IV Large Scale Test Facility (LSTF). Results obtained from an experiment with an opening in the cold leg showed core boiling and, then, core uncoveries, first associated with the loop seal clearing and subsequently due to long-term core boil-off. The influence of the noncondensible gas (air) was found to be significant for the steam condensation behavior especially in the SG U-tubes. This greatly affected the primary pressurization rate and also the loop seal clearing phenomenon. CAHTARE 2 code post-test analysis resulted in qualitative agreement with the data. (author)

Additional details

Additional titles

Subtitle (English)
ROSA-IV/LSTF experiment and analysis

Publishing Information

Publisher
Japan Society of Mechanical Engineers.
Imprint Place
Tokyo (Japan)
Imprint Title
The 1st JSME/ASME joint international conference on nuclear engineering
Imprint Pagination
1273 p.
Journal Page Range
v. 2 p. 209-214.

Conference

Title
1. JSME/ASME joint international conference on nuclear engineering.
Dates
4-7 Nov 1991.
Place
Tokyo (Japan).

Optional Information

Notes
Imprint:Composed of two volumes.