A Hypothetical Accident of a Sodium Cooled Fast Breeder Reactor as a Basis for the Design of a Prismatic Concrete Containment System

No Thumbnail Available

Date

1971-09-20T00:00:00+00:00

Advisors

Journal Title

Series/Report No.

J - Analysis of Shell Structures: Containment
J3 - Containment of Power Reactor Plants - I
SMiRT 1 - Berlin, Germany. September 20-24, 1971

Journal ISSN

Volume Title

Publisher

IASMiRT

Abstract

Description

Keywords

Citation

Degree

Discipline