CRITICAL EXPERIMENTS AND CHARACTERISTICS MEASUREMENT FOR JRR-2

Technical Report · Fri Dec 01 04:00:00 EST 1961

OSTI ID:4817252

JRR-2, the second research reactor, is a thermal reactor, using the MTR- type fuel of 20% enriched U, with heavy water both as moderator and coolant. The maximum thermal output and the mean thermal flux of the reactor are 10 Mw and 1 x 10/sup 14/ n/cm/sup 2//sec. The results of the various characteristic measurements on the reactor performed during a 4-month period after criticality was reached are presented. Included are results of critical experiments, calibration of control rods, reflecting effect of the upper part of heavy water, reactivity effect of fuel elements, characteristic measurement of the temperature coefficient, measurement of the distribution of the thermal fluxes, and calibration of the power output. (auth)

• Research Organization: Japan Atomic Energy Research Inst., Tokyo
• NSA Number: NSA-16-025022
• OSTI ID: 4817252
• Report Number(s): JAERI-1025
• Country of Publication: Japan
• Language: Japanese

Related Subjects

ACIDS
COATING
CONTROL ELEMENTS
CRITICALITY
DIFFUSION
DISTRIBUTION
ENRICHMENT
FUEL ELEMENTS
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
JRR-2
LIQUIDS
MATERIALS TESTING
MEASURED VALUES
NEUTRON FLUX
NITRIC ACID
ORGANIC FLUORINE COMPOUNDS
POLYETHYLENES
POLYMERS
POWER
REACTIVITY
REACTOR TECHNOLOGY
REFLECTORS
RESEARCH REACTORS
TEMPERATURE
THERMAL NEUTRONS
VARIATIONS
WATER