Published October 1991 | Version v1
Report Restricted

Tests in the ATLE Loop on the PIUS design

  • 1. ABB Atom AB, Vasteras (Sweden)

Description

The self-protective thermal hydraulic design of the primary system that prevents reactor power from exceeding the coolant capability of the submerging water independent of outside surveillance and supervision is a fundamental feature of the PIUS design. The experimental demonstration of the self-protective features of the primary system in a large scale test loop (the ATLE Loop) in the ABB Atom Engineering Laboratories are described in the paper. The volume scale of the ATLE Loop is approximately 1:300. The height of the test loop is the same as in the full scale design to ensure similarity in the driving buoyancy force during a transient. The test loop includes the following: one electrically heated, simulated fuel assembly, reactor pool, primary systems, upper and lower density locks and heat exchangers. System response to various severe transients and normal operations was studied. Comparisons were made with the predictions of the RIGEL code, which has been developed by ABB Atom specifically for study of the PIUS design and its predecessor designs. Selected results of these studies and comparison of these results with predictions obtained using RIGEL are presented in this paper

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Title
Transactions of the nineteenth water reactor safety information meeting
Imprint Pagination
220 p.
Journal Page Range
p. 3.1.
Report number
NUREG/CP--0118

Conference

Title
19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
Dates
28-30 Oct 1991.
Place
Bethesda, MD (United States).

Optional Information

Secondary number(s)
CONF-911079--.