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Commercial utilization of weapon grade plutonium as TRISO fuel in conventional CANDU reactors

Oluşturulma Tarihi:

Niteleme Bilgileri

Tür: Makale

Yayınlanma Durumu: Yayınlanmış

Dosya Biçimi: Dosya Yok

Dil: İngilizce

Konu(lar): TEKNOLOJİ,

Yazar(lar): Şahin, Sümer (Yazar), Şahin, Hacı Mehmet (Yazar), Acır, Adem (Yazar),

Emeği Geçen(ler):


Yayın Tarihi: 25-11-2015 Yayın Niteleme Bilgileri: Kaynağın tam metnine ulaşmak için URL’ ye tıklayınız.


Dosya:
Dosya Yok

Anahtar Kelimeler

CANDU; TRISO; Carbide fuel; Weapon grade plutonium; High burn up



    Özet

    Large quantities of weapon grade (WG) plutonium have been accumulated in the nuclear warheads. Plutonium and heavy water moderator can give a good combination with respect to neutron economy. TRISO type fuel can withstand very high fuel burn up levels. The paper investigates the prospects of utilization of TRISO fuel made of WG-plutonium in CANDU reactors.

    Three different fuel compositions have been investigated: (1): 90% ThC + 10% PuC, (2): 70% ThC + 30% PuC and (3): 50% ThC + 50% PuC. The temporal variation of the criticality k and the burn-up values of the reactor have been calculated by full power operation up to 17 years. Calculated startup criticalities for these fuel modes arek∞,0 = 1.6403, 1.7228 and 1.7662, respectively.

    Attainable burn up values and reactor operation times without new fuel charge will be 94 700, 265 000 and 425 000 MW.D/MT and along with continuous operation periods of ∼3.5, 10 and 17 years, respectively, for the corresponding modes. These high burn ups would reduce fuel fabrication costs and nuclear waste mass for final disposal per unit energy drastically.



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    Notlar



    Kaynakça[1]Oelrich I. Missions for nuclear weapons after the cold war occasional. Federation of American Scientists, Paper No. 3; January 2005.[2]India Unveils Thorium Reactor. [25.08.05].[3]DiRicco DJ. Thorium Fuels Safer Reactor Hopes. Novastar Resources Ltd. [29.01.06].[4]IAEA. Potential of thorium based fuel cycles to constrain plutonium and reduce long lived waste toxicity. IAEA-TECDOC-1349. International Atomic Energy Agency, Vienna, Austria; 2003.[5]N. Ponomarev-Stepnoi, D. TsourikovRussian plutonium policyNucl Eng Des, 173 (1997), pp. 293–299Article | PDF (584 K) | View Record in Scopus | Citing articles (8)[6]N. Ponomarev-StepnoiNuclear power of the 21st centuryNucl Eng Des, 173 (1997), pp. 21–31Article | PDF (808 K) | View Record in Scopus[7]Koudriatsev E, et al. Use of weapons-grade plutonium from dismantled nuclear weapons for the peaceful objective of electric power generation – AIDA /MOX 2. In: Proceedings, GLOBAL2003, 2, 1855–1862, New Orleans, LA [November 16–20, 2003].[8]P.N. Alekseev, V.V. Ignatiev, S.A. Konakov, et al.Harmonization of fuel cycles for nuclear energy system with the use of molten salt technologyNucl Eng Des, 173 (1997), pp. 151–158Article | PDF (567 K) | View Record in Scopus | Citing articles (12)[9]A.I. Kiryushin, et al.Project of the GT-MHR high-temperature helium reactor with gas turbineNucl Eng Des, 173 (1997), pp. 119–129Article | PDF (743 K) | View Record in Scopus | Citing articles (72)[10]N. Kodochigov, et al.Neutronic features of the GT-MHR reactorNucl Eng Des, 222 (2003), pp. 161–171Article | PDF (559 K) | View Record in Scopus[11]H. Akie, T. Muromura, H. Takano, S. MatsuuraA new fuel material for once-through weapons plutonium burningNucl Technol, 107 (1994), p. 182Full Text via CrossRef[12]T. Yamashita, H. Akie, Y. Nakano, K. Kuramoto, N. Nitani, T. NakamuraCurrent status of researches on the plutonium rock-like oxide fuel and its burning in light water reactors”Prog Nucl Energy, 38 (3–4) (2001), pp. 327–330Article | PDF (322 K) | View Record in Scopus | Citing articles (7)[13]Boczar PG, Dyck GR, Chan PSW, Buss DB. Recent advances in thorium fuel cycles for CANDU reactors, thorium fuel utilization: options and trends. In: Proceedings of three IEAE meetings held in Vienna in 1997, 1998 and 1999, IEAE-TECDOC-1319, 104–120, International Atomic Energy Agency, Vienna, Austria; 2002.[14]Critoph E. Prospects for self-sufficient equilibrium thorium cycles in CANDU reactors. Report AECL-5501. Atomic Energy of Canada Ltd., Canada; 1976.[15]V. Jagannathan, Pal Usha, R. Karthikeyan, S. Ganesan, R.P. Jain, S.U. KamatATBR-A thorium breeder reactor concept for early induction of thorium in an enriched uranium reactorNucl Technol, 133 (2001), pp. 1–31[16]E.P. Loewen, R.D. Wilson, J.K. Hohorst, A.S. KumarPreliminary frapcon-3th steady-state fuel analysis of ThO2 and UO2 fuel mixturesNucl Technol, 136 (2001), pp. 261–277View Record in Scopus | Citing articles (14)[17]S. Şahin, K. Yıldız, H.M. Şahin, N. Şahin, A. AcırIncreased fuel burn up in a CANDU thorium reactor using weapon grade plutoniumNucl Eng Des, 236 (17) (2006), pp. 1780–1790[18]S. Şahin, K. Yıldız, H.M. Şahin, A. AcırInvestigation of CANDU reactors as a thorium burnerEnergy Convers Manage, 47 (13–14) (2006), pp. 1661–1675Article | PDF (309 K) | View Record in Scopus[19]S. Şahin, K. Yıldız, H.M. Şahin, N. Şahin, A. Acır, N. Şahin, T. AltınokMinor actinide burning in a CANDU thorium reactorKerntechnik, 71 (5–6) (2006), pp. 247–257View Record in Scopus | Full Text via CrossRef[20]Campbell EM, Venneri F. Modular helium-cooled reactor. Internal Report, General Atomics; July 2006.[21]Miller CM, Scheffel WJ. Post irradiation examination and evaluation of peach bottom FTE-13. General atomics document 906939; November 1985.[22]Talamo A. Advanced in-core fuel cycles for the gas turbine modular helium reactor, royal institute of technology. Stockholm, Doctoral Thesis; 2006.[23]A. Talamo, W. Gudowski, F. VenneriThe burnup capabilities of the deep burn modular helium reactor analyzed by the monte carlo continuous energy code MCBAnn Nucl Energy, 31 (2004), pp. 173–196Article | PDF (1056 K) | View Record in Scopus[24]Sefidvash F. Fixed Bed Nuclear Reactor (FBNR). Status of small reactor designs without on-site refueling, IAEA-TECDOC-1536; January 2007. p. 373–86).[25]S. Şahin, F. SefidvashThe fixed bed nuclear reactor conceptEnergy Convers Manage, 49 (7) (2008), pp. 1902–1909Article | PDF (862 K) | View Record in Scopus[26]S. Şahin, H.M. Şahin, A. AcırCriticality and burn up evolutions of the fixed bed nuclear reactor with alternative fuelsEnergy Convers Manage, 51 (9) (2010), pp. 1781–1787Article | PDF (1380 K) | View Record in Scopus | Citing articles (16)[28]Woodhead LW, Ingolfsrud LJ, Performance of Canadian commercial nuclear units and heavy water plants. Paper presented at European Nuclear Conference, 21 April 1975, Paris, France. Summary in Transaction American Nuclear Society, vol. 20; 1975. p. 160.[29]Alkan M, Reutilization of nuclear fuel wastes. PhD thesis in Turkish, Gazi University, Institute of Science and Technology, Ankara, Turkey; 2003.[30]S. Şahin, K. Yıldız, A. AcırPower flattening in the fuel bundle of a CANDU reactorNucl Eng Des, 232 (1) (2004), pp. 7–18Article | PDF (234 K) | View Record in Scopus[31]S. Şahin, H.M. Şahin, A. AcırUtilization of TRISO fuel with reactor grade plutonium in CANDU reactorsNucl Eng Des, 240 (8) (2010), pp. 2066–2074Article | PDF (1760 K) | View Record in Scopus | Citing articles (9)[32]A.M. Weinberg, E.P. WignerThe physical theory of neutron chain reactorsThe University of Chicago Press (1959)[33]S. Şahin, Radiation shielding calculations for fast reactors (in Turkish), Gazi University, Publication # 169, Faculty of Science and Literature, Publication number 22, Ankara, Türkiye; 1991.[34]Petrie LM. SCALE5-Scale System Driver, NUREG/CR-0200, Revision 7, Volume III, Section M1, ORNL/NUREG/CSD-2/V3/R7, Oak Ridge National Laboratory; 2004.[35]Greene NM, Petrie LM. XSDRNPM, A one-dimensional discrete-ordinates code for transport analysis, NUREG/CR-0200, Revision 7, 2, Section F3, ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory; 2004.[36]Jordan WC, Bowman SM, Hollenbach DF. Scale cross-section libraries, NUREG/CR-0200, Revision 7, 3, section M4, ORNL/NUREG/CSD-2/V3/R7, Oak Ridge National Laboratory; 2004.[37]Garber DI, et al. Angular distributions in neutron-induced reactions. BNL-400, Brookhaven National Laboratory; July 1970.[38]Landers NF, Petrie LM, Hollenbach DF. CSAS, Control module for enhanced criticality safety analysis sequences. NUREG/CR-0200, Revision 6, 1, Section C4, ORNL/NUREG/CSD-2/V1/R7, Oak Ridge National Laboratory; 2004.[39]Greene NM. BONAMI, resonance self-shielding by the bondarenko method. NUREG/CR-0200, Revision 6, 2, Section F1, ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory; 2004.[40]Greene NM, Petrie LM, Westfall RM. NITAWL-III, Scale system module for performing resonance shielding and working library production. NUREG/CR-0200, Revision 6, 2, Section F2, ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory; 2004.[41]S. Şahin, H.M. Şahin, M. Alkan, K. YıldızAn assessment of thorium and spent lwr-fuel utilization potential in CANDU reactorsEnergy Convers Manage, 45 (2004), pp. 1067–1085Article | PDF (442 K) | View Record in Scopus | Citing articles (22)


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