Application of backtracking algorithm to depletion calculations
Description
Based on the theory of linear chain method for analytical depletion calculations, the burn-up matrix is decoupled by the divide and conquer strategy and the linear chain with Markov characteristic is formed. The density, activity and decay heat of every nuclide in the chain can be calculated by analytical solutions. Every possible reaction path of the nuclide must be considered during the linear chain establishment process. To confirm the calculation precision and efficiency, the algorithm which can cover all the reaction paths of the nuclide and search the paths automatically according to to problem description and precision restrictions should be sought. Through analysis and comparison of several kinds of searching algorithms, the backtracking algorithm was selected to search and calculate the linear chains using Depth First Search (DFS) method. The depletion program can solve the depletion problem adaptively and with high fidelity. The solution space and time complexity of the program were analyzed. The new developed depletion program was coupled with Monte Carlo program MCMG-II to calculate the benchmark burn-up problem of the first core of China Experimental Fast Reactor (CEFR). The initial verification and validation of the program was performed by the calculation. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 10 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042523
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATOR DRIVEN TRANSMUTATION; ANALYTICAL SOLUTION; BENCHMARKS; BURNUP; CEFR REACTOR; COMPUTER CODES; MARKOV PROCESS; MONTE CARLO METHOD; NUCLEAR SAFETY PILOT PLANT; PLUTONIUM 239; RADIATION PROTECTION; REACTOR CORES; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; EPITHERMAL REACTORS; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FAST REACTORS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATHEMATICAL SOLUTIONS; MINUTES LIVING RADIOISOTOPES; NUCLEI; PLUTONIUM ISOTOPES; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR SAFETY EXPERIMENTS; REACTORS; RESEARCH AND TEST REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; STOCHASTIC PROCESSES; TRANSMUTATION; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1065760.pdf; 12 refs., 6 figs., 4 tabs.