Fast reactor response matrix nodal analysis

Thesis/Dissertation · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6135637

Anaf, J

A general nodal coupling scheme, including a number of common options as special cases, under a response matrix form, has been utilized within the one-group light water reactor code SIMULATE. In this work an extension to multigroup was developed and implemented in the nodal test code SIMMG. It was tested to demonstrate that the assumptions associated with the extension of the formalism were satisfactory for fast reactor situations. A number of nodal options were applied to a range of cases involving configurations of importance in fast reactors. Among those options: coarse mesh diffusion theory, modified coarse mesh diffusion theory, nodal expansion method, to second order, and to fourth order, one particular options, reflection based coarse mesh theory, has yielded consistently better results than the other methods considered. The results obtained were compared to fine mesh calculations, using the code 2DB, and they show that nodal methods, in the response matrix form used in the Simulate Multigroup formalism, may be applied to fast reactor problems with very good results and savings.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY (USA)
• OSTI ID: 6135637
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CODES
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
EPITHERMAL REACTORS
EQUATIONS
FAST REACTORS
GROUP THEORY
KINETICS
MATHEMATICS
MESH GENERATION
NEUTRON DIFFUSION EQUATION
REACTOR KINETICS
REACTORS
S CODES
SIMULATION