Development and Validation of A Nuclear Fuel Cycle Analysis Tool: A FUTURE Code
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
Description
This paper presents the development and validation methods of the FUTURE (FUel cycle analysis Tool for nUcleaR Energy) code, which was developed for a dynamic material flow evaluation and economic analysis of the nuclear fuel cycle. This code enables an evaluation of a nuclear material flow and its economy for diverse nuclear fuel cycles based on a predictable scenario. The most notable virtue of this FUTURE code, which was developed using C and MICROSOFT SQL DBMS, is that a program user can design a nuclear fuel cycle process easily using a standard process on the canvas screen through a drag-and-drop method. From the user's point of view, this code is very easy to use thanks to its high flexibility. In addition, the new code also enables the maintenance of data integrity by constructing a database environment of the results of the nuclear fuel cycle analyses
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 45
- Journal Issue
- 5
- Series
- 20 refs, 13 figs, 6 tabs
- Journal Page Range
- p. 665-674
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 46131211
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- DESIGN; F CODES; FUEL CYCLE; MAINTENANCE; NUCLEAR FUELS; VALIDATION
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; REACTOR MATERIALS; TESTING