Reactor Physics Quarterly Report (April, May, June 1970)

Technical Report · Sat Aug 01 04:00:00 EDT 1970

DOI:https://doi.org/10.2172/4114532· OSTI ID:4114532

Schmid, L. C. ^[1]; Clayton, E. D. ^[1]; Heineman, R. E. ^[1]

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

Updates include: (1) Thermal Reactors, including Calculations of Power Distributions and Reactivities, Nonlinear Least-Squares Data Analyses, Critical Experiments in UO₂-4 wt% PuO₂ Fueled-H₂O Moderated Assemblies, Burnup Data from the PRTR Batch Core Experiment, Gulf General Atomic Spectral Data, Pu-H₂O Lattice Subcritical Experiments, Interpretation of k_∞for Water Moderated UO₂-PuO₂ Lattices, BRT-I: Battelle-Revised-THERMOS-I, BMC-I: The Battelle Monte Carlo Code, HRG-3, DBUFIT-I: A Least Squares Analysis Code for Nuclear Burnup Data, Code Development, Burnup Calculations for BNW 1 Fuel Pins, k_∞ Measurement for ThO₂-²³⁵UC₂-C HTGR Lattice as a Function of Temperature, HTLTR Temperature Coefficient, HTLTR Reactor Pressure Control, Calculations of HTLTR Safety Rod Temperature Distributions; (2) Fast Reactors, including PCTR Measurements of k_∞ for a UA1 Fast Core.

• 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-24-046122
• OSTI ID: 4114532
• Report Number(s): BNWL-1381-2
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALUMINUM ALLOYS-- CONFIGURATION-- FAST NEUTRONS-- MULTIPLICATION FACTORS-- PCTR-- PLUTONIUM OXIDES-- REACTOR CORE-- REACTOR LATTICES-- RESEARCH REACTORS-- URANIUM ALLOYS-- URANIUM DIOXIDE-- URANIUM 235-- WATER MODERATOR
BNW 1 Fuel Pins
BURNUP-- CHEMICAL ANALYSIS-- FUELS-- PRTR-- RESEARCH REACTORS-- SPECTROSCOPY
BURNUP-- CONFIGURATION-- DISTRIBUTION-- FAST REACTORS-- FUEL CANS-- FUEL ELEMENTS-- MULTIPLICATION FACTORS-- PLUTONIUM OXIDES-- POWER-- REACTOR CORE-- REACTOR LATTICES-- REACTORS-- STAINLESS STEELS-- THERMAL NEUTRONS-- URANIUM DIOXIDE-- WATER MODERATED REACTORS
Battelle Monte Carlo Code
Burnup
CAF ASSEMBLY-- CONFIGURATION-- CRITICAL ASSEMBLIES-- CRITICALITY-- FUELS-- MASS-- PLUTON
Criticality
DBUFIT-I
Fast Reactors
Function
HRG-3
HTLTR
Lattice
N38510 --Research & Test Reactors & Critical Assemblies--Kinetics & Dynamics
N38930* --Reactor Theory--Experimental Applications
Nuclear Criticality Safety Program (NCSP)
PCTR Measurements
Temperature
Thermal Reactors
UA1 Fast Core