Development of restructuring template for MELCOR
- 1. Korea Atomic Energy Research Institute, KAERI (Korea, Republic of)
Description
In order to develop a template for the MELCOR computer code, the current data saving and transferring methods used in MELCOR were analyzed first, and then a restructured module for the SPR package was developed to be applied to MELCOR. The current MELCOR code ensures a fixed-size storage for 4 different data types, and manages the input-dependent data size by storing the data on the stacked packages. It uses a pointer variable to identify the variables between the packages. This technique causes difficult grasping of the meaning of the variables as well as a waste of memory. New features of FORTRAN90, in the meantime, make it possible to allocate the storage dynamically and to use the user-defined data type, which leads to restructured module development for the SPR package. Efficient memory treatment and an easy understanding of the code have been benefits from this developed module. The validation of the template has been done by comparing the results of the modified code with those from the existing code, and it has confirmed that the results were the same. The template for the SPR package could allow for the extension of the template to the entire code. It has expected that the template would accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models. (author)
Additional details
Publishing Information
- Publisher
- Universal Academy
- Imprint Place
- Tokyo (Japan)
- ISBN
- 4-946443-64-9
- Imprint Title
- PSAM 5: Probabilistic safety assessment and management
- Imprint Pagination
- 2820 p.
- Journal Page Range
- p. 2541-2546
Conference
- Title
- 5. international conference on probabilistic safety assessment and management
- Acronym
- PSAM 5
- Dates
- 27 Nov - 1 Dec 2000
- Place
- Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32039058
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; DATA BASE MANAGEMENT; HAZARDS; HEAT TRANSFER; M CODES; MODIFICATIONS; NUCLEAR POWER; NUCLEAR POWER PLANTS; PRESSURE DROP; PROGRAMMING LANGUAGES; REACTOR ACCIDENTS; RISK ASSESSMENT; SAFETY ANALYSIS; SPRAYS; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; MANAGEMENT; NUCLEAR FACILITIES; POWER; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- Vol. 4/4; 6 refs., 4 figs., 1 tab. Imprint:Published in 4 volumes, also available on CD-ROM can be used for Windows 95/98/2000, Macintosh and UNIX. Also published in Frontiers Science Series No.34, ISSN 0915-8502