Automation of safety parameters of the IEA-R1 reactor
- 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Engenharia Nuclear
Description
This study aims the development of a computational program that manages the execution of various programs of calculation methodology of the safety parameters of IEA-R1 reactor, making the process more practical and safe. Making, therefore, the treatment of data of input and output of each programs, an automatic process. This work transformed a series of existing programs in a sub-routine of a principal program, that is, a program that calls each program automatically as it is necessary, and also created some other programs to manipulate data to be used by others and so make the process practical and safe. Among the used programs can be mentioned some of the main as HAMMER-TECHNION responsible by calculating the macroscopic cross sections, TWODB for the calculation of the reactor core and burn of the fuel elements and CITATlON responsible by core calculating in three dimensions. The result obtained proved to be totally compatible with that found in Manual calculation methodology performed by the team responsible for the IEA-R1.4 reactor
Additional details
Additional titles
- Original title (Portuguese)
- Automatizacao dos parametros de seguranca do reator IEA-R1
Publishing Information
- Journal Title
- Revista Brasileira de Pesquisa e Desenvolvimento
- Journal Volume
- 12
- Journal Issue
- 3
- Journal Page Range
- p. 141-145
- ISSN
- 0104-7698
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 43081580
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AUTOMATION; C CODES; CALCULATION METHODS; CRITICALITY; CROSS SECTIONS; DELAYED NEUTRON FRACTION; FUEL ELEMENTS; H CODES; IEAR-1 REACTOR; REACTIVITY COEFFICIENTS; REACTOR CORES; REACTOR SAFETY; T CODES
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS