Published 1987 | Version v1
Book

Progress with algorithm and vector/parallel enhancements for Relap5/Mod2 thermohydraulic system simulation code

  • 1. Idaho National Engineering Lab., Idaho Falls, ID (USA)

Description

Earlier experience resulting from attempts to develop a parallel implementation, and a vector implementation for RELAP5/MOD1, using super computers, resulted in an analysis suggesting a five to ten times performance enhancement for future versions of the code. The MOD2 version of the code, presently available, uses a six equation model (vs. five equations in MOD1) with the option of a semi-implicit or nearly-implicit numerical solution scheme. The nearly-implicit numerical scheme violates the convective (material) Courant limit. The RELAP5/MOD2 code has been implemented on CDC Cyber 176, CRAY 1S and CRAY X-MP/48 computers. Algorithm performance enhancements and vector performance improvements have been measured and are analyzed for these three computing machines. The reactor small break loss-of-coolant problem, used in previous studies, was employed as the basis for the present analysis. Previous studies performed to compare the performance of algorithms in MOD2 are compared to MOD1, using the two presently available numerical methods in MOD2. Planned vector and parallel enhancements are discussed in the context of past studies, and expected future performance gains. Applicability of the RELAP5 code to best estimate real time simulations and nuclear power plant simulators is discussed

Part of:
Advances in Reactor physics, mathematics and computation. Volume 3

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire.
Imprint Place
Paris (France)
Imprint Title
Advances in Reactor Physics, Mathematics and Computation. Volume 3
Imprint Pagination
709 p.
Journal Page Range
p. 1421-1432.

Conference

Title
International Topical Meeting on Advances in Reactor Physics, Mathematics and Computation.
Dates
27-30 Apr 1987.
Place
Paris (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
22063934
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; FLUID FLOW; HYDRAULICS; PARALLEL PROCESSING; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; THERMODYNAMICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; PROGRAMMING; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract DE-AC07-76ID01570