Validation and verification summary report for GRIMHX and TRIMHX
As part of the code Certification process, codes used by Reactor Physics to calculate values in Technical Specifications or Safety Analyses must undergo formal Validation and Verification. GRIMHX and TRIMHX are codes used in such a manner. This report summarizes and consolidates the work done to date on the Validation and Verification of these two codes. GRIMHX is a 3-D static reactor code which uses finite difference algorithms to solve the neutron diffusion equation in hex-z geometry. TRIMHX is the time dependent version of GRIMHX and solves the delayed neutron precursor equations in addition to the neutron diffusion equation. Both of these codes were developed at SRS in the early 1970s.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5038892
- Report Number(s):
- WSRC-TR-90-594; ON: DE92015060
- Country of Publication:
- United States
- Language:
- English
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Verification, validation, and benchmarking report for TRIMHX: A three dimensional hexagonal transient diffusion theory code
Verification, validation, and benchmarking report for TRIMHX: A three dimensional hexagonal transient diffusion theory code
Related Subjects
220100* -- Nuclear Reactor Technology-- Theory & Calculation
663610 -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
COMPUTER CODES
DELAYED NEUTRON PRECURSORS
DIFFERENTIAL EQUATIONS
EQUATIONS
FINITE DIFFERENCE METHOD
G CODES
ISOTOPES
ITERATIVE METHODS
MATHEMATICAL LOGIC
NEUTRON DIFFUSION EQUATION
NUMERICAL SOLUTION
PHYSICS
RADIOISOTOPES
REACTOR PHYSICS
SAFETY ANALYSIS
T CODES
TESTING
VALIDATION
VERIFICATION