4 Matching Results

Search Results

Advanced search parameters have been applied.

Benchmarking of the 99-group ANSL-V library

Description: The purpose of this paper is to present thermal benchmark data testing results for the BAPL-1, TRX-1, and SEEP-1 lattices, using selected processed cross-sections from the ANSL-V 99-group library. 7 refs., 1 tab.
Date: January 1, 1987
Creator: Wright, R.Q.; Ford, W.E. III; Greene, N.M.; Petrie, L.M.; Primm, R.T. III & Westfall, R.M.
Partner: UNT Libraries Government Documents Department

Verification and validation plan for reactor analysis computer codes

Description: This report presents a verification and validation (V V) plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations. This plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River (DOE-SR) as identified in a letter to R.E. Tiller (Reference 1). The plan stresses verification and validation by demonstrating successful application of the codes to predict reactor data, special measurements, and benchmarks. This is in compliance with the intent of the WSRC quality assurance requirements. Restructuring of software especially to achieve verification compliance is not recommended.
Date: November 1, 1989
Creator: Toffer, H.; Crowe, R.D.; Schwinkendorf, K.N. (Westinghouse Hanford Co., Richland, WA (United States)) & Pevey, R.E. (Westinghouse Savannah River Co., Aiken, SC (United States))
Partner: UNT Libraries Government Documents Department

A technique for code validation for criticality safety calculations

Description: There are probably as many techniques to validate computer codes for criticality safety purposes as there are computer codes and code validators. One method used at Martin Marietta Energy Systems, Inc., to validate the KENO code and associated cross sections consists of determining a single-sided, uniform-width, closed-interval, lower tolerance band for k{sub eff} of critical systems. For application, this lower tolerance band becomes the upper safety limit (USL) acceptance criteria for subcriticality based upon the KENO calculations. A system is considered acceptably subcritical if a calculated k{sub eff} plus 2 standard deviations lies below this upper safety limit (i.e., k{sub eff} + 2{sigma} < USL). 5 refs., 1 fig.
Date: January 1, 1991
Creator: Dyer, H.R.; Jordan, W.C. (Oak Ridge National Lab., TN (United States)) & Cain, V.R. (Oak Ridge Y-12 Plant, TN (United States))
Partner: UNT Libraries Government Documents Department

Validation and verification summary report for GRIMHX and TRIMHX

Description: 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.
Date: December 1, 1990
Creator: Trumble, E.F.
Partner: UNT Libraries Government Documents Department