Technical Activities Quarterly Report: AEC Reactor Development and Technology Programs (July, August, September 1971)

Technical Report · Wed Dec 01 04:00:00 EST 1971

DOI:https://doi.org/10.2172/4700331· OSTI ID:4700331

Schmid, L. C. ^[1]

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1. Battelle Pacific Northwest Labs., Richland, WA (United States)

Updates include: (1) High Temperature Reactor Physics, including Measurement of Physics Parameters for an MSBR Lattice in the HTLTR, and Reactivity Measurements for a ThO₂-PuO₂ HTGR Lattice in the HTLTR as a Function of Temperature; (2) Steady State and Transient Subchannel Code Development and Data Analysis, including COBRA-III Computer Program; (3) Effect of ²⁴¹Pu on Criticality Safety Limits for ²³⁹Pu; (4) Nuclear Graphite, including In-Reactor Creep, Radiolytic Reactions in Graphite Moderated Reactors, Effect of Sample Size on Dimensional Stability of Graphite, High Temperature Irradiations, and Mechanism of Irradiation Damage; (5) Phoenix Fuel Studies, including Documentation, and Data Collection.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(45-1)-1830
• NSA Number: NSA-26-011326
• OSTI ID: 4700331
• Report Number(s): BNWL-1522-4
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BURNUP-- FUEL PLATES-- ISOTOPE RATIO-- MTR-- REACTOR CORE
CARBON DIOXIDE-- CARBON MONOXIDE-- COOLANT LOOPS-- HELIUM-- HTGR TYPE REACTORS-- HYDROGEN-- MIXTURES-- PRODUCTION-- RADIOLYSIS-- VAPORS-- WATER
CRITICALITY-- ISOTOPE RATIO-- PLUTONIUM NITRATES-- PLUTONIUM 241-- SAFETY
Code Development
Criticality
Data Collection
Documentation
FLUID FLOW-- FUEL ELEMENTS-- GAS COOLED REACTORS-- HEAT TRANSFER-- HTGR TYPE REACTORS-- HTLTR-- MOCKUP-- MSBR-- MULTIPLICATION FACTORS-- PERFORMANCE-- PLUTONIUM OXIDES-- PROGRAMMING-- REACTOR KINETICS-- REACTOR LATTICES-- THORIUM OXIDES
Graphite Moderated Reactors
N20330 --Chemistry-- Radiation & Nuclear Chemistry--Radiolysis
N38100* --Power Reactor Development
Nuclear Criticality Safety Program (NCSP)
Nuclear Graphite
Phoenix Fuel Studies
Plutonium
Quarterly Report
Radiolytic Reactions
Reactor Development
Reactor Physics
Steady State
Technology Programs
Transient Subchannel
Uranium