National Energy Software Center: benchmark problem book. Revision
Computational benchmarks are given for the following problems: (1) Finite-difference, diffusion theory calculation of a highly nonseparable reactor, (2) Iterative solutions for multigroup two-dimensional neutron diffusion HTGR problem, (3) Reference solution to the two-group diffusion equation, (4) One-dimensional neutron transport transient solutions, (5) To provide a test of the capabilities of multi-group multidimensional kinetics codes in a heavy water reactor, (6) Test of capabilities of multigroup neutron diffusion in LMFBR, and (7) Two-dimensional PWR models.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6926543
- Report Number(s):
- ANL-7416-Suppl.3; ON: DE86012678
- Resource Relation:
- Other Information: Paper copy only, copy does not permit microfiche production. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
Similar Records
Argonne Code Center: benchmark problem book
REACTOR PHYSICS AND MATHEMATICS TECHNICAL PROGRESS REPORT FOR THE PERIOD DECEMBER 1, 1959 TO MARCH 1, 1960
Static benchmarking of the NESTLE advanced nodal code
Technical Report
·
Wed Jun 01 00:00:00 EDT 1977
·
OSTI ID:6926543
REACTOR PHYSICS AND MATHEMATICS TECHNICAL PROGRESS REPORT FOR THE PERIOD DECEMBER 1, 1959 TO MARCH 1, 1960
Technical Report
·
Mon Oct 31 00:00:00 EST 1960
·
OSTI ID:6926543
Static benchmarking of the NESTLE advanced nodal code
Conference
·
Thu May 01 00:00:00 EDT 1997
·
OSTI ID:6926543
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
NEUTRON TRANSPORT THEORY
COMPUTER CALCULATIONS
BENCHMARKS
FINITE DIFFERENCE METHOD
NEUTRON DIFFUSION EQUATION
REACTOR PHYSICS
DIFFERENTIAL EQUATIONS
EQUATIONS
ITERATIVE METHODS
NUMERICAL SOLUTION
PHYSICS
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation
NEUTRON TRANSPORT THEORY
COMPUTER CALCULATIONS
BENCHMARKS
FINITE DIFFERENCE METHOD
NEUTRON DIFFUSION EQUATION
REACTOR PHYSICS
DIFFERENTIAL EQUATIONS
EQUATIONS
ITERATIVE METHODS
NUMERICAL SOLUTION
PHYSICS
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation