Quasi solution of radiation transport equation

Journal Article · Sun Oct 01 00:00:00 EDT 1995 · Nuclear Science and Engineering

OSTI ID:131677

Pogosbekyan, L R; Lysov, D A ^[1]

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1. All-Russian Research Inst. for Nuclear Power Plant Operation, Moscow (Russian Federation)

There is uncertainty with experimental data as well as with input data of theoretical calculations. The neutron distribution from the variational principle, which takes into account both theoretical and experimental data, is obtained to increase the accuracy and speed of neutronic calculations. The neutron imbalance in mesh cells and the discrepancy between experimentally measured and calculated functional of the neutron distribution are simultaneously minimized. A fast-working and simple-programming iteration method is developed to minimize the objective functional. The method can be used in the core monitoring and control system for (a) power distribution calculations, (b) in- and ex-core detector calibration, (c) macro-cross sections or isotope distribution correction by experimental data, and (d) core and detector diagnostics.

• OSTI ID: 131677
• Journal Information: Nuclear Science and Engineering, Vol. 121, Issue 2; Other Information: PBD: Oct 1995
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
REACTOR CONTROL SYSTEMS
REACTOR MONITORING SYSTEMS
NEUTRON DIFFUSION EQUATION
ITERATIVE METHODS
DATA COVARIANCES
VARIATIONAL METHODS
POWER DISTRIBUTION
REACTOR CORES
REACTOR INSTRUMENTATION
PHOTON TRANSPORT
GAMMA TRANSPORT THEORY
USES