Methods for Calculating the Reactor Periods of Multi-Region Reactors

Journal Article · Wed Nov 01 00:00:00 EST 1961 · J. At. Energy Soc. Japan

DOI:https://doi.org/10.3327/jaesj.3.841· OSTI ID:4820937

An, S

Methods for calculating the reactor periods of multiregion reactors by multigroup theory are dnnscussed. lt is usually very difficult to solve the kinetic problems of multiregnnon reactors by a strict and straight forward method. Therefore, two kinds of approximation, the perturbation method and the method of coupled system parameters, are used under the condition that the system is nearly critical. In the former, introducing a vector, the elements of which consist of neutron fluxes and delayed neutron precursor concentrations, a formula is derived which relates the variation of the reactor periods to the perturbation conditions. The equation relating the reactivity with the steady reactor period is also obtained. In the latter, the coupled parameters concerning the neutron source terms of every energy group in every region are defined, and the kinetic equation which gives the steady period is derived using such parameters.

• Research Organization: Tokyo Univ.
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: NONE
• NSA Number: NSA-16-006123
• OSTI ID: 4820937
• Journal Information: J. At. Energy Soc. Japan, Journal Name: J. At. Energy Soc. Japan Vol. Vol: 3
• Country of Publication: Country unknown/Code not available
• Language: Japanese

Related Subjects

CONFIGURATION
CRITICALITY
DELAYED NEUTRONS
ENERGY
ENERGY RANGE
EPITHERMAL NEUTRONS
EQUATIONS
FAST NEUTRONS
GROUP THEORY
INHOURS
NEUTRON FLUX
NEUTRON SOURCES
Nuclear Criticality Safety Program (NCSP)
NUMERICALS
PROMPT NEUTRONS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RESONANCE NEUTRONS
THERMAL NEUTRONS
TRANSIENTS
VARIATIONS
ZONES