Published January 1984 | Version v1
Report Metadata-only

Overview of the HDR-containment tests

Creators

  • 1. Battelle-Institut e.V., Frankfurt, Germany
  • 2. Kernforschungszentrum Karlsruhe, Germany

Description

In this paper, a review of the HDR containment experiments of Phase I of the HDR Safety Program is given together with a first comparison with a variety of pretest calculations by German, French and American codes. An outlook to the experiments planned during Phase II in 1984 and 1985 concludes this paper

Additional details

Publishing Information

Imprint Title
Eleventh water reactor safety research information meeting. Volume 3. Containment systems research; status of source term reassessment; fuel systems research program; risk analysis
Journal Page Range
p. 258-324.
Report number
NUREG/CP--0048-Vol.3

Conference

Title
11. NRC water reactor safety research information meeting.
Dates
14-24 Oct 1983.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16010905
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BLOWDOWN; COMPARATIVE EVALUATIONS; COMPUTER CODES; CONCRETES; CONTAINMENT SYSTEMS; HDR REACTOR; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; STEELS; TRANSIENTS
Descriptors DEC
ACCIDENTS; ALLOYS; BUILDING MATERIALS; BWR TYPE REACTORS; CARBON ADDITIONS; CONTAINMENT; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS