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Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles
KTH, Superseded Departments, Physics.
KTH, Superseded Departments, Physics.
2004 (English)In: Journal of Nuclear Science and Technology, ISSN 0022-3131, E-ISSN 1881-1248, Vol. 41, no 12, 1228-1236 p.Article in journal (Refereed) Published
Abstract [en]

We performed a numerical comparative analysis of the burnup capability of the Gas Turbine-Modular Helium Reactor (GT-MHR) by the Monte Carlo Continuous Energy Burnup Code (MCB). The MCB code is an extension of MCNP that includes the burnup implementation; it adopts continuous energy cross sections and it evaluates the transmutation trajectories for over 2,400 decaying nuclides. We equipped the MCB code with three different nuclear data libraries: JENDL-3.2, JEF-2.2 and ENDF/B-6.8 processed for temperatures from 300 to 1,800 K.

The GT-MHR model studied in this paper is fueled by actinides coming from the Light Water Reactors waste, converted into two different types of fuel: Driver Fuel and Transmutation Fuel. The Driver Fuel supplies the fissile nuclides needed to maintain the criticality of the reactor, whereas the Transmutation Fuel depletes non-fissile isotopes and controls reactivity excess. We set the refueling and shuffling period to one year and the in-core fuel residency time to three years.

The comparative analysis of the MCB code consists of accuracy and precision studies. In the accuracy studies, we performed the burnup calculation with different nuclear data libraries during the year at which the refueling and shuffling schedule set the equilibrium of the fuel composition. In the precision studies, we repeated the same simulations 20 times with a different pseudorandom number stride and the same nuclear data library.

Place, publisher, year, edition, pages
2004. Vol. 41, no 12, 1228-1236 p.
Keyword [en]
GT-MHR, JENDL, JEF, ENDF/B, TRISO, gas-cooled, graphite-moderated, plutonium, burnup
National Category
Atom and Molecular Physics and Optics
Identifiers
URN: urn:nbn:se:kth:diva-5545DOI: 10.3327/jnst.41.1228ISI: 000227001800012Scopus ID: 2-s2.0-13244277620OAI: oai:DiVA.org:kth-5545DiVA: diva2:9945
Note
QC 20100922Available from: 2006-04-05 Created: 2006-04-05 Last updated: 2017-11-21Bibliographically approved
In thesis
1. Advanced In-Core Fuel Cycles for the Gas Turbine-Modular Helium Reactor
Open this publication in new window or tab >>Advanced In-Core Fuel Cycles for the Gas Turbine-Modular Helium Reactor
2006 (English)Doctoral thesis, comprehensive summary (Other scientific)
Abstract [en]

In 1789 a German chemist, Martin Heinrich Klaproth, announced the discovery of a new element: uranium; few years later, the head of father of the modern chemistry, Antoine Lavoisier, was swept away by guillotine: a new era was destined to be opened, either where energy would have been produced in large scale by nuclear processes delivering hundreds of times the energy of chemical processes or where a mass of people, revolutionary or not, would have been melted down into a couple of seconds. After a quite long time, on the 2nd December 1942, the first nuclear reactor has been put into operation by Enrico Fermi in Chicago; few years later, came also the dark side utilization of fissile materials in Hiroshima and Nagasaki. Since those moments, three power plants generations succeeded, until the current one which is the generation IV of nuclear reactors. The latter has the goal of generating electricity in a safe manner, for the core is designed to provide an effective passive cooling of the decay heat. Amid generation IV of nuclear power plants, the Gas Turbine – Modular Helium Reactor, designed by General Atomics, is the only core with an energy conversion efficiency of 50%; the above consideration, coupled to construction and operation costs lower than ordinary Light Water Reactors, renders the Gas Turbine – Modular Helium reactor rather unequaled.

In the present studies we investigated the possibility to operate the GT-MHR with two types of fuels: LWRs waste and thorium; since thorium is made of only fertile 232Th, we tried to mix it with pure 233U, 235U or 239Pu; ex post facto, only uranium isotopes allow the reactor operation, that induced us to examine the possibility to use a mixture of uranium, enriched 20% in 235U, and thorium. We performed all calculations by the MCNP and MCB codes, which allowed to model the reactor in a very detailed threedimensional geometry and to describe the nuclides transmutation in a continuous energy approach; finally, we completed our studies by verifying the influence of the major nuclear data libraries, JEFF, JENDL and ENDF/B, on the obtained results.

Place, publisher, year, edition, pages
Stockholm: KTH, 2006. x,60 p.
Series
TRITA-FYS, ISSN 0280-316X ; 2006.25
National Category
Atom and Molecular Physics and Optics
Identifiers
urn:nbn:se:kth:diva-3901 (URN)91-7178-328-8 (ISBN)
Public defence
2006-04-21, Sal FA31, AlvaNova, Roslagstullsbacken 21, Stockholm, 14:00
Opponent
Supervisors
Note

QC 20100922

Available from: 2006-04-05 Created: 2006-04-05 Last updated: 2014-12-17Bibliographically approved

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