Nuclear reactors -- Containment

Evaluation of the HDR fire test data and accompanying computational activities with conclusion from present code capabilities

by Jason Floyd, Lothar Wolf, and John Krawiec

Design, Instrumentation and Testing of a Steel Containment Vessel Model

V. K. Luk

Description of current and planned research in structural engineering

G Bagchi

Mark II containment lead plant program load evaluation and acceptance criteria.

U.S. Nuclear Regulatory Commission. Division of Systems Safety.

Estimate of radionuclide release characteristics into containment under severe accident conditions: final report

prepared by H.P. Nourbakhsh.

Evaluation of AP600 Containment Thermal-hydraulic Performance

K. M. Campe

Identification and assessment of containment and release management strategies for a BWR Mark I containment

prepared by C.C. Lin, J.R. Lehner.

Istechenie teplonositeli͡a︡ pri potere germetichnosti reaktornogo kontura

[V.V. Fisenko, B.M. T͡S︡izin, I͡U︡.A. Kalaĭda, V.V. Arsentʹev].

Ductile to brittle toughness transition characterization of A533B steel

prepared by J.A. Joyce.

Unresolved safety issues: pressurized thermal shock : oversight hearing before the Subcommittee on Oversight and Investigations of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-seventh Congress, second session, on unresolved safety issues, pressurized thermal shock; hearing held in Washington, D.C., May 7, 1982.

United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Oversight and Investigations.