Published October 2013 | Version v1
Journal article

Development and Validation of A Nuclear Fuel Cycle Analysis Tool: A FUTURE Code

  • 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