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Title: Dry process dependency of dupic fuel cycle

Abstract

During the Dry Process, volatile and semi-volatile elements are released from the fuel. The effects of these released radioactive nuclides on DUPIC fuel cycle are analyzed from the view-point of radiation hazard, decay beat, and hazard index. Radiation hazard of fresh and spent DUPIC fuel is sensitive to the method of Dry Process. Decay beat of the fuel is also affected. Hazard index turned out not to be dependent on Dry Process.

Authors:
; ; ;  [1]
  1. Kyunghee Univ. (Korea, Republic of)
Publication Date:
OSTI Identifier:
476573
Report Number(s):
CONF-960804-Vol.3
TRN: 97:009114
Resource Type:
Conference
Resource Relation:
Conference: SPECTRUM `96: international conference on nuclear and hazardous waste management, Seattle, WA (United States), 18-23 Aug 1996; Other Information: PBD: 1996; Related Information: Is Part Of Proceedings of the international topical meeting on nuclear and hazardous waste management (SPECTRM `96): Volume 3; PB: 843 p.
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; CANDU TYPE REACTORS; FUEL CYCLE; SPENT FUELS; REPROCESSING; PWR TYPE REACTORS

Citation Formats

Park, Kwangheon, Whang, Juho, Kim, Yun-goo, and Kim, Heemoon. Dry process dependency of dupic fuel cycle. United States: N. p., 1996. Web.
Park, Kwangheon, Whang, Juho, Kim, Yun-goo, & Kim, Heemoon. Dry process dependency of dupic fuel cycle. United States.
Park, Kwangheon, Whang, Juho, Kim, Yun-goo, and Kim, Heemoon. 1996. "Dry process dependency of dupic fuel cycle". United States. doi:.
@article{osti_476573,
title = {Dry process dependency of dupic fuel cycle},
author = {Park, Kwangheon and Whang, Juho and Kim, Yun-goo and Kim, Heemoon},
abstractNote = {During the Dry Process, volatile and semi-volatile elements are released from the fuel. The effects of these released radioactive nuclides on DUPIC fuel cycle are analyzed from the view-point of radiation hazard, decay beat, and hazard index. Radiation hazard of fresh and spent DUPIC fuel is sensitive to the method of Dry Process. Decay beat of the fuel is also affected. Hazard index turned out not to be dependent on Dry Process.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1996,
month =
}

Conference:
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  • Safeguards have been applied to the R and D process for directly fabricating CANDU fuel with PWR spent fuel material. Safeguards issues to be resolved were identified in the areas such as international cooperation on handling foreign origin nuclear material, technology development of operator's measurement system of the bulk handling process of spent fuel material, and a built-in C/S system for independent verification of material flow. The fuel cycle concept (Direct Use of PWR spent fuel in CANDU, DUPIC) was developed in consideration of reutilization of over-flowing spent fuel resources at PWR sites and a reduction of generated high levelmore » wastes. All those safeguards issues have been finally resolved, and the first batch of PWR spent fuel material was successfully introduced in the DUPIC lab facility and has been in use for routine process development.« less
  • The AMBIDEXTER is an integral-type molten-salt reactor system, having been designed for the GEN IV requirements with a denatured thorium-uranium fuel cycle. And the DUPIC fuel cycle, recognized as a highly transparent reprocessing method for the PWR spent fuel, was developed through Korea-Canada-U.S. collaboration. This paper demonstrates a closed uranium-thorium fuel cycle strategy for a PWR and MSR symbiont via combining these two. This fuel cycle improves its transparency in the nuclear proliferation aspect and it does its economics in the spent-fuel management aspect. Fluorination uranium content in the PWR spent fuel, in the aftermath of which the remnants aremore » composed of fluorides of residual uranium, plutonium, minor actinides and non-volatile fission-products, and are to be used as the feedstock of initial and daily loads of the AMBIDEXTER. Thorium fluoride is admixed at early operating stage to suppress the reactivity increase rate due to burnout of the initially loaded fission products, and through the reactor lifetime to compensate the transmutation and fission losses. On the bypass line linked to the fuel-salt recirculation stream in the reactor system, a small-scale on-line fluorination unit evaporates surplus uranium daily-fed, but not yet converted to plutonium. As {sup 232}Th converts into {sup 233}U, the maximum of 1.67% fissile uranium enrichment was achieved presently, that can improve the economics when used in PWR fuel. (authors)« less
  • A heterogeneous thorium fuel recycle scenario in a Canada deuterium uranium (CANDU) reactor has been analyzed by the dynamic analysis method. The thorium recycling is performed through a dry process which has a strong proliferation resistance. In the fuel cycle model, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 0%. In this analysis, the spent fuel inventory as well as the amount of plutonium, minor actinides, and fission products of a multiple thorium recycling fuel cycle were estimated and compared to thosemore » of the once-through fuel cycle. The analysis results have shown that the heterogeneous thorium fuel cycle can be constructed through the dry process technology. It is also shown that the heterogeneous thorium fuel cycle can reduce the spent fuel inventory and save on the natural uranium resources when compared with the once-through cycle. (authors)« less
  • Through the US Department of Energy (DOE)/Korean Ministry of Science and Technology (MOST) bilateral arrangement for safeguards R and D, the Korean Atomic Energy Research Institute (KAERI) and Los Alamos National Laboratory (LANL) is developing safeguards process for DUPIC. DUPIC is a process to reconstitute spent PWR fuel as CANDU fuel to power CANDU reactors. Novel safeguards approaches are needed to verify a material balance for this process because the high radioactivity of the spent fuel precludes, or at least hinder, traditional measurements. Safeguards research and development for DUPIC will involve unattended continuous monitoring and include the development of neutronmore » coincidence counting measurement instruments, the development of a materials accountability system, simulation and statistical analysis of measurement systems, and training. An INVS neutron measurement instrument has been delivered to KAERI and initial tests have been performed. Simulation activities to date have been focused on a hot-cell experiment and will be expanded to model measurements for a pilot plant. A demonstration of a visual imaging and radiation monitoring system is planned for the KAERI hot-cells. These and future development plans are discussed.« less
  • For both pressurized water reactor (PWR) and Canada deuterium uranium (CANDU) tandem analysis, the Direct Use of spent PWR fuel In CANDU reactor (DUPIC) fuel cycle in a CANDU 6 reactor is studied using the DRAGON/DONJON chain of codes with the ENDF/B-V and ENDF/B-VI libraries. The reference feed material is a 17 x 17 French standard 900-MW(electric) PWR fuel. The PWR spent-fuel composition is obtained from two-dimensional DRAGON assembly transport and depletion calculations. After a number of years of cooling, this defines the initial fuel nuclide field in the CANDU unit cell calculations in DRAGON, where it is further depletedmore » with the same neutron group structure. The resulting macroscopic cross sections are condensed and tabulated to be used in a full-core model of a CANDU 6 reactor to find an optimized channel fueling rate distribution on a time-average basis. Assuming equilibrium refueling conditions and a particular refueling sequence, instantaneous full-core diffusion calculations are finally performed with the DONJON code, from which both the channel power peaking factors and local parameter effects are estimated. A generic study of the DUPIC fuel cycle is carried out using the linear reactivity model for initial enrichments ranging from 3.2 to 4.5 wt% in a PWR. Because of the uneven power histories of the spent PWR assemblies, the spent PWR fuel composition is expected to differ from one assembly to the next. Uneven mixing of the powder during DUPIC fuel fabrication may lead to uncertainties in the composition of the fuel bundle and larger peaking factors in CANDU. A mixing method for reducing composition uncertainties is discussed.« less