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 |