A visualization program of the Li reduction process for PWR spent fuel
- 1. Korea Atomic Energy Research Institute, Taejeon (Korea, Republic of)
Description
To predict the amounts of metals produced from the metalization process of PWR spent fuel, the GC code, which simulates the Li process, was developed and a program, which is similar with it, was also developed recently. Since the latter provides only the calculating results, it is necessary that the program is improved to one with a user-friendly interface. In this paper, the program was upgraded in order that users can not only accurately understand the metalization process by the Li reduction method but also access its input or output data easily. In this paper, the recent developed program for numerically simulating the Li reduction process of PWR spent fuel was improved from its execution and data visualization aspects. It is possible that, through its interface, a user can directly set or control its condition variables and obtain the resulting data in various forms. It is also expected that this program could be applied to simulate the ACP process
Additional details
Publishing Information
- Publisher
- Korean Radioactive Waste Society
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Radioactive Waste Society Autumn 2006
- Imprint Pagination
- 393 p.
- Journal Page Range
- p. 314-315
Conference
- Title
- Korean Radioactive Waste Society Autumn 2006
- Dates
- 16-17 Nov 2006
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38113942
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- G CODES; PWR TYPE REACTORS; REDUCTION; SPENT FUELS
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs, 1 fig