Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960

doi:10.2172/4135055

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960

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Description

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Physical Description

xiv, 211 p. : ill. ; 28 cm.

Creation Information

Aerojet-General Corporation July 31, 1960.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 94 times. More information about this report can be viewed below.

Publisher

Aerojet-General Nucleonics
Place of Publication: San Ramon, California

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UNT Libraries Government Documents Department

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Titles

Added Title: ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SEMIANNUAL PROGRESS REPORT FOR JANUARY 1-JUNE 30, 1960
Main Title: Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Serial Title: Army Gas-Cooled Reactor Systems Program Progress Report
Added Title: U.S. Atomic Energy Commission Idaho Operations Office Report IDO-28558

Description

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Physical Description

xiv, 211 p. : ill. ; 28 cm.

Notes

NTIS

Gas Cooled Reactor Experiment I. Expedient modifications to the tube bundle and control rods made possible the attainment of initial critical of the GCRE-I reactor early in February. The scheduled series of low-power experiments was completed and the facility shut down in midApril to permit the permanent modification to the tube bundle, control rods, and instrumentation. Gas Cooled Reactor Experiment II. Work on the GCRE-II was limited to materials development and systems studies. These studies included mobile and portable power systems using homogeneous graphite reactors as well as modifications and improvements to the ML-1 system. The materials development effort was devoted to homogeneous graphite fuel materials. The ML-1. Activation measurements were made in the Lid Tank Facility. Reanalysis of stresses in the tube sheet indicated high stresses in certain regions. Design of most of the reactor package was completed and fabrication initiated. An alloy (80% Ag--15% In--5% Cd) was selected for the ML- 1 control blades on the basis of ductility tests, corrosion tests, and neutronic calculations. A critical experiment was performed on the ML-1 configuration with pin type fuel elements. The recuperator design selected is a four-pas-s shell and tube heat exchanger. Fuel-element Development. A preliminary design study indicated that the seven-pin fuel element does not significantly improve performance over that obtainable with the 19-pin design. A corrosion test specimen of Hastelloy X exposed for 5000 hr in air at 1750 deg F showed 0.0016- in. penetration. Beryllium oxide-- uranium oxide capsule irradiation was completed with about 2 at.% U/sup 235/ burn-up at maximum surface temperature of 1740 deg F. The IB-2T-Z irradiation test was completed after about 800 hr of operation, including 1147 thermal cycles between 1000 and 1600 deg F without any evidence of malfunction. The irradiation of the GCRE-1 plate type element (1-3P) was completed after 429 hr of operation. (For preceding period see IDO-28549.) (W.L.H.)

Other Information: Orig. Receipt Date: 31-DEC-60

Subjects

Keywords

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Language

English

Item Type

Report

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

Report No.: IDO-28558
Grant Number: AT(10-1)-880
Digital Object Identifier: https://doi.org/10.2172/4135055
Office of Scientific & Technical Information Report Number: 4135055
OCLC: 727224963
SuDoc Number: Y 3.At 7:22/IDO-28558
Archival Resource Key: ark:/67531/metadc863304

Relationships

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960, ark:/67531/metadc67300/

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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