Parallel computation of multigroup reactivity coefficient using iterative method
- Center for Development of Nuclear Informatics, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)
- Center for Nuclear Fuel Technology, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)
One of the research activities to support the commercial radioisotope production program is a safety research target irradiation FPM (Fission Product Molybdenum). FPM targets form a tube made of stainless steel in which the nuclear degrees of superimposed high-enriched uranium. FPM irradiation tube is intended to obtain fission. The fission material widely used in the form of kits in the world of nuclear medicine. Irradiation FPM tube reactor core would interfere with performance. One of the disorders comes from changes in flux or reactivity. It is necessary to study a method for calculating safety terrace ongoing configuration changes during the life of the reactor, making the code faster became an absolute necessity. Neutron safety margin for the research reactor can be reused without modification to the calculation of the reactivity of the reactor, so that is an advantage of using perturbation method. The criticality and flux in multigroup diffusion model was calculate at various irradiation positions in some uranium content. This model has a complex computation. Several parallel algorithms with iterative method have been developed for the sparse and big matrix solution. The Black-Red Gauss Seidel Iteration and the power iteration parallel method can be used to solve multigroup diffusion equation system and calculated the criticality and reactivity coeficient. This research was developed code for reactivity calculation which used one of safety analysis with parallel processing. It can be done more quickly and efficiently by utilizing the parallel processing in the multicore computer. This code was applied for the safety limits calculation of irradiated targets FPM with increment Uranium.
- OSTI ID:
- 22218070
- Journal Information:
- AIP Conference Proceedings, Vol. 1554, Issue 1; Conference: PIPS-2013: Padjadjaran international physics symposium 2013: Contribution of physics on environmental and energy conservations, Padjadjaran (Indonesia), 7-9 May 2013; Other Information: (c) 2013 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CRITICALITY
DIFFUSION EQUATIONS
FISSION PRODUCTS
HIGHLY ENRICHED URANIUM
IRRADIATION
ISOTOPE PRODUCTION
ITERATIVE METHODS
MOLYBDENUM
REACTIVITY COEFFICIENTS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
RESEARCH REACTORS
SAFETY ANALYSIS
STAINLESS STEELS