Restructuring of burnup sensitivity analysis code system by using an object-oriented design approach
Creators
- 1. O-arai Engineering Center, Japan Nuclear Cycle Development Institute (JNC), Ibaraki (Japan)
- 2. Kumatori Works, Nuclear Fuel Industries, Ltd. (NFI), Osaka (Japan)
Description
A new burnup sensitivity analysis code system was developed with help from the object-oriented technique and written in Python language. It was confirmed that they are powerful to support complex numerical calculation procedure such as reactor burnup sensitivity analysis. The new burnup sensitivity analysis code system PSAGEP was restructured from a complicated old code system and reborn as a user-friendly code system which can calculate the sensitivity coefficients of the nuclear characteristics considering multicycle burnup effect based on the generalized perturbation theory (GPT). A new encapsulation framework for conventional codes written in Fortran was developed. This framework supported to restructure the software architecture of the old code system by hiding implementation details and allowed users of the new code system to easily calculate the burnup sensitivity coefficients. The framework can be applied to the other development projects since it is carefully designed to be independent from PSAGEP. Numerical results of the burnup sensitivity coefficient of a typical fast breeder reactor were given with components based on GPT and the multicycle burnup effects on the sensitivity coefficient were discussed. (authors)
Availability note (English)
Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)Additional details
Publishing Information
- Publisher
- SFEN
- Imprint Place
- Paris (France)
- Imprint Pagination
- 12 p.
- Report number
- INIS-FR--09-0974
Conference
- Title
- international topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications
- Acronym
- M and C 2005
- Dates
- 12-15 Sep 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 40084836
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTER CALCULATIONS; P CODES; PERTURBATION THEORY; PROGRAMMING LANGUAGES; SENSITIVITY ANALYSIS; VALIDATION
- Descriptors DEC
- COMPUTER CODES; TESTING
Optional Information
- Notes
- 6 refs.