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

Technical Report · Wed Dec 01 00:00:00 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
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
• 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
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
Nuclear Criticality Safety Program (NCSP)
Criticality
Quarterly Report
Reactor Development
Technology Programs
Reactor Physics
Plutonium
Uranium
Nuclear Graphite
Phoenix Fuel Studies
Documentation
Data Collection
Steady State
Transient Subchannel
Code Development
Radiolytic Reactions
Graphite Moderated Reactors
N38100* -Power Reactor Development
N20330 -Chemistry- Radiation & Nuclear Chemistry-Radiolysis