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Title: ENGINEERING AND CONSTRUCTING THE HALLAM NUCLEAR POWER FACILITY REACTOR STRUCTURE

Abstract

The Hallam Nuclear Power Facility reactor structure, including the cavity liner, is described, and the design philosophy and special design requirements which were developed during the preliminary and final engineering phases of the project are explained. The structure was designed for 600 deg F inlet and 1000 deg F outlet operating sodium temperatures and fabricated of austenitic and ferritic stainless steels. Support for the reactor core components and adequate containment for biological safeguards were readily provided even though quite conservative design philosophy was used. The calculated operating characteristics, including heat generation, temperature distributions and stress levels for full-power operation, are summarized. Ship fabrication and field installation experiences are also briefly related. Results of this project have established that the sodium graphite reactor permits practical and economical fabrication and field erection procedures; considerably higher operating design temperatures are believed possible without radical design changes. Also, larger reactor structures can be similarly constructed for higher capacity (300 to 1000 Mwe) nuclear power plants. (auth)

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Atomics International. Div. of North American Aviation Inc., Canoga Park, Calif.
OSTI Identifier:
4765176
Report Number(s):
NAA-SR-7366
NSA Number:
NSA-16-031260
DOE Contract Number:  
AT(11-1)-GEN-8
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; CONFINEMENT; COOLANT LOOPS; DISTRIBUTION; ECONOMICS; EQUATIONS; FABRICATION; FLUID FLOW; GRAPHITE MODERATOR; HEATING; HIGH TEMPERATURE; LIQUID METAL COOLANT; MECHANICAL STRUCTURES; PLANNING; POWER; POWER PLANTS; RADIATION PROTECTION; REACTORS; STAINLESS STEELS; TEMPERATURE; THERMAL STRESSES

Citation Formats

Mahlmeister, J E, Haberer, W V, Casey, D F, Susnir, J, Ricci, T, and Peck, W S. ENGINEERING AND CONSTRUCTING THE HALLAM NUCLEAR POWER FACILITY REACTOR STRUCTURE. United States: N. p., 1960. Web. doi:10.2172/4765176.
Mahlmeister, J E, Haberer, W V, Casey, D F, Susnir, J, Ricci, T, & Peck, W S. ENGINEERING AND CONSTRUCTING THE HALLAM NUCLEAR POWER FACILITY REACTOR STRUCTURE. United States. doi:10.2172/4765176.
Mahlmeister, J E, Haberer, W V, Casey, D F, Susnir, J, Ricci, T, and Peck, W S. Thu . "ENGINEERING AND CONSTRUCTING THE HALLAM NUCLEAR POWER FACILITY REACTOR STRUCTURE". United States. doi:10.2172/4765176. https://www.osti.gov/servlets/purl/4765176.
@article{osti_4765176,
title = {ENGINEERING AND CONSTRUCTING THE HALLAM NUCLEAR POWER FACILITY REACTOR STRUCTURE},
author = {Mahlmeister, J E and Haberer, W V and Casey, D F and Susnir, J and Ricci, T and Peck, W S},
abstractNote = {The Hallam Nuclear Power Facility reactor structure, including the cavity liner, is described, and the design philosophy and special design requirements which were developed during the preliminary and final engineering phases of the project are explained. The structure was designed for 600 deg F inlet and 1000 deg F outlet operating sodium temperatures and fabricated of austenitic and ferritic stainless steels. Support for the reactor core components and adequate containment for biological safeguards were readily provided even though quite conservative design philosophy was used. The calculated operating characteristics, including heat generation, temperature distributions and stress levels for full-power operation, are summarized. Ship fabrication and field installation experiences are also briefly related. Results of this project have established that the sodium graphite reactor permits practical and economical fabrication and field erection procedures; considerably higher operating design temperatures are believed possible without radical design changes. Also, larger reactor structures can be similarly constructed for higher capacity (300 to 1000 Mwe) nuclear power plants. (auth)},
doi = {10.2172/4765176},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {12}
}