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Modeling report of DYMOND code (DUPIC version)

Abstract

The DYMOND code employs the ITHINK dynamic modeling platform to assess the 100-year dynamic evolution scenarios for postulated global nuclear energy parks. Firstly, DYMOND code has been developed by ANL(Argonne National Laboratory) to perform the fuel cycle analysis of LWR once-through and LWR-FBR mixed plant. Since the extensive application of DYMOND code has been requested, the first version of DYMOND has been modified to adapt the DUPIC, MSR and RTF fuel cycle. DYMOND code is composed of three parts; the source language platform, input supply and output. But those platforms are not clearly distinguished. This report described all the equations which were modeled in the modified DYMOND code (which is called as DYMOND-DUPIC version). It divided into five parts;Part A deals model in reactor history which is included amount of the requested fuels and spent fuels. Part B aims to describe model of fuel cycle about fuel flow from the beginning to the end of fuel cycle. Part C is for model in re-processing which is included recovery of burned uranium, plutonium, minor actinide and fission product as well as the amount of spent fuels in storage and disposal. Part D is for model in other fuel cycle which is  More>>
Authors:
Park, Joo Hwan; [1]  Yacout, Abdellatif M [2] 
  1. KAERI, Taejon (Korea, Republic of)
  2. Argonne National Laboratory, Ilinois (United States)
Publication Date:
Apr 01, 2003
Product Type:
Technical Report
Report Number:
KAERI/TR-2472/2003
Resource Relation:
Other Information: 10 refs, 10 figs, 4 tabs; PBD: Apr 2003
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; D CODES; FUEL CYCLE; NUCLEAR ENERGY; PLUTONIUM; REACTOR OPERATION; SPENT FUEL STORAGE; SPENT FUELS; THORIUM
OSTI ID:
20594267
Research Organizations:
KAERI, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
TRN: KR0500919041573
Availability:
Available from INIS in electronic form
Submitting Site:
KRN
Size:
71 pages
Announcement Date:

Citation Formats

Park, Joo Hwan, and Yacout, Abdellatif M. Modeling report of DYMOND code (DUPIC version). Korea, Republic of: N. p., 2003. Web.
Park, Joo Hwan, & Yacout, Abdellatif M. Modeling report of DYMOND code (DUPIC version). Korea, Republic of.
Park, Joo Hwan, and Yacout, Abdellatif M. 2003. "Modeling report of DYMOND code (DUPIC version)." Korea, Republic of.
@misc{etde_20594267,
title = {Modeling report of DYMOND code (DUPIC version)}
author = {Park, Joo Hwan, and Yacout, Abdellatif M}
abstractNote = {The DYMOND code employs the ITHINK dynamic modeling platform to assess the 100-year dynamic evolution scenarios for postulated global nuclear energy parks. Firstly, DYMOND code has been developed by ANL(Argonne National Laboratory) to perform the fuel cycle analysis of LWR once-through and LWR-FBR mixed plant. Since the extensive application of DYMOND code has been requested, the first version of DYMOND has been modified to adapt the DUPIC, MSR and RTF fuel cycle. DYMOND code is composed of three parts; the source language platform, input supply and output. But those platforms are not clearly distinguished. This report described all the equations which were modeled in the modified DYMOND code (which is called as DYMOND-DUPIC version). It divided into five parts;Part A deals model in reactor history which is included amount of the requested fuels and spent fuels. Part B aims to describe model of fuel cycle about fuel flow from the beginning to the end of fuel cycle. Part C is for model in re-processing which is included recovery of burned uranium, plutonium, minor actinide and fission product as well as the amount of spent fuels in storage and disposal. Part D is for model in other fuel cycle which is considered the thorium fuel cycle for MSR and RTF reactor. Part E is for model in economics. This part gives all the information of cost such as uranium mining cost, reactor operating cost, fuel cost etc.}
place = {Korea, Republic of}
year = {2003}
month = {Apr}
}