A METHOD OF ANALYSIS ON REACTOR SPATIAL KINETICS ON CALDER HALL TYPE REACTOR

Journal Article · Fri Jan 01 04:00:00 EST 1960 · J. Atomic Energy Soc. Japan

DOI:https://doi.org/10.3327/jaesj.2.175· OSTI ID:4166998

Takeda, A

>In the core of a large power reactor the neutron flux shape tends to be distorted in transient behavior. Especially in cores with positive temperature coefficient, such as the improved Calder Hall type reactor, the distortibn becomes unstable, resulting in divergence or oscillation. In order to control such a reactor a spatis: control system should be provided such thrt control rods are locally divided into several groups and each group of control rods is independently moved to control local reactivity. Kinetic analysis of such a reactor requires a method which can describe the time behavior of neutron flux shape and temperature distribution in the core. A new method using the mode transfer functions, corresponding to spatial eigenfunctions, is proposed. Applying thia method the spatial kinetic analysis can be resolved into each mode kinetic analysis without any spatial consideration. (auth)

• Research Organization: Japan Atomic Power Co.
• Sponsoring Organization: USDOE
• NSA Number: NSA-14-015473
• OSTI ID: 4166998
• Journal Information: J. Atomic Energy Soc. Japan, Journal Name: J. Atomic Energy Soc. Japan Vol. Vol: 2
• Country of Publication: Country unknown/Code not available
• Language: Japanese

Related Subjects

CONFIGURATION
CONTROL ELEMENTS
DISTRIBUTION
EQUATIONS
GAS COOLANT
GRAPHITE MODERATOR
MOTION
NEUTRON FLUX
OSCILLATIONS
POWER PLANTS
REACTIVITY
REACTOR KINETICS
REACTOR TECHNOLOGY
REACTORS
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
VARIATIONS