NESTLE: Few-group neutron diffusion equation solver utilizing the nodal expansion method for eigenvalue, adjoint, fixed-source steady-state and transient problems

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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 … continued below

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147 p.

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Turinsky, P. J.; Al-Chalabi, R. M. K.; Engrand, P.; Sarsour, H. N.; Faure, F. X. & Guo, W. June 1, 1994.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 84 times, with 5 in the last month. More information about this report can be viewed below.

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  • EG & G Idaho
    Publisher Info: EG and G Idaho, Inc., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho
  • Los Alamos National Laboratory
    Publisher Info: Los Alamos National Lab., NM (United States)
    Place of Publication: New Mexico

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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.

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147 p.

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OSTI; NTIS; INIS; GPO Dep.

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  • Other Information: PBD: Jun 1994

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  • June 1, 1994

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  • Jan. 12, 2019, 4:41 p.m.

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Turinsky, P. J.; Al-Chalabi, R. M. K.; Engrand, P.; Sarsour, H. N.; Faure, F. X. & Guo, W. NESTLE: Few-group neutron diffusion equation solver utilizing the nodal expansion method for eigenvalue, adjoint, fixed-source steady-state and transient problems, report, June 1, 1994; Idaho Falls, Idaho. (https://digital.library.unt.edu/ark:/67531/metadc1399965/: accessed April 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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