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Office of Scientific & Technical Information Technical Reports
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Office of Scientific & Technical Information Technical Reports
33
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Gas-Cooled Reactor Project Progress Report
1
Irradiation Processing Department Monthly Record Report
1
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Gas-Cooled Reactor Project Progress Report
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Irradiation Processing Department Monthly Record Report
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1960
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Office of Scientific & Technical Information Technical Reports
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Measurement of Coefficients of Reactivity. 0 EFPH. Core I, Seed 2. (T- 550132). Section 1
Semi-final report (report No. 3) E-N load conversion ratios
100-K Area electrical power system load and voltage study for project CG-775. Revision
Final report on program for using X-8001 aluminum alloy cladding material for Hanford fuel elements: PT-IP-43-A-84-MT, IP-80-A-91-FP and IP-2-I-99-FP
Fuels Preparation Department monthly report, January 1960
Radiochemistry for the rupture of a Zircaloy-2 clad seven rod cluster fuel element in KER Loop 2
Production Test IP-300-A: Irradiation of twenty inch natural uranium tube and tube elements with hot headed inner tubes
Expansion task force: Old reactors speed of control for no overbore cases
Irradiation Processing Department Monthly Record Report: December 1959
Provisional Process Specifications for the Attachment of Support Rails by Electrical Resistance Spot Welding
Potential for process tube burnout during transient conditions
Proposed solid state diffusion bonding (SSDB) process: Gas pressure bonding
Request to procure plutonium: Project No. HW-2724(19), Request No. HLO-471.
A CORROSION STUDY OF WELDED STAINLESS STEEL FUEL ELEMENTS
Current status -- Second generation process tube internal corrosion
Irradiation Processing Department, monthly record report, February, 1960
Piping changes for increased production at B, D, DR, F, C, and H reactors
Chemical Processing Department monthly report for January 1960
Chemical Processing Department monthly report for July 1960
Idaho Chemical Processing Plant Tributyl Phosphate Extraction of Uranium From Ammonium Nitrate Solutions
An Investigation of the Structural Integrity of Selected Components of the Oak Ridge Research Reactor
PERIODIC RADIATION SURVEY OF REACTOR PLANT CONTAINER AND COMPONENTS AFTER SHUTDOWN. CORE I, SEED I. SECTION 3. Test Results (T-612076)
Radial Temperature Profile of Sodium Pool Boiling Heater Assembly
STUDIES OF THE USE OF COAGULANT AIDS IN THE LIME-SODA TREATMENT OF LARGE- VOLUME, LOW-LEVEL RADIOACTIVE LIQUID WASTE
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