OSTI Document ID 10191160
Local PDF osti/10191160.pdf
Title NESTLE: Few-group neutron diffusion equation solver utilizing the nodal expansion method for eigenvalue, adjoint, fixed-source steady-state and transient problems
Creators/
Authors
Turinsky, P.J.; Al-Chalabi, R.M.K.; Engrand, P.; Sarsour, H.N.; Faure, F.X.; Guo, W. [North Carolina State Univ., Raleigh, NC (United States)]
Publication Date 1994 Jun 01
Description/
Abstract
NESTLE is a FORTRAN77 code that solves the few-group neutron diffusion equation utilizing the Nodal Expansion Method (NEM). NESTLE can solve the eigenvalue (criticality); eigenvalue adjoint; external fixed-source steady-state; or external fixed-source. or eigenvalue initiated transient problems. The code name NESTLE originates from the multi-problem solution capability, abbreviating Nodal Eigenvalue, Steady-state, Transient, Le core Evaluator. The eigenvalue problem allows criticality searches to be completed, and the external fixed-source steady-state problem can search to achieve a specified power level. Transient problems model delayed neutrons via precursor groups. Several core properties can be input as time dependent. Two or four energy groups can be utilized, with all energy groups being thermal groups (i.e. upscatter exits) if desired. Core geometries modelled include Cartesian and Hexagonal. Three, two and one dimensional models can be utilized with various symmetries. The non-linear iterative strategy associated with the NEM method is employed. An advantage of the non-linear iterative strategy is that NSTLE can be utilized to solve either the nodal or Finite Difference Method representation of the few-group neutron diffusion equation.
OSTI ID 10191160
Report Numbers line line docnumall
Other ID Numbers ON: DE95001903
Document Type Technical Report
Research Organization EG and G Idaho, Inc., Idaho Falls, ID (United States); Los Alamos National Lab., NM (United States)
Sponsor Organization USDOE, Washington, DC (United States)
DOE Contract Numbers AC07-76ID01570;W-7405-ENG-36
Bibliographic Source INEEL
Country United States
Language English
Pages/Size 147 p.
System Entry Date 1994 Nov 25
Subject Category Code 22 GENERAL STUDIES OF NUCLEAR REACTORS;66 ;99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
Descriptors NEUTRON DIFFUSION EQUATION; N CODES; NODAL EXPANSION METHOD; MULTIGROUP THEORY; HYDRODYNAMIC MODEL; HEAT TRANSFER; HYDRAULICS
Availability INIS ; OSTI as DE95001903
Notes PBD: Jun 1994
Reference Numbers SCA: 220100;663600;990200; PA: EDB-94:159429;NTS-95:004515;INS-94:022698;ERA-20:000801; SN: 94001261937