Optimization of spatial structure designs of control rod using Monte Carlo code RMC

Hao LUO , Mancang LI , Shanfang HUANG , Minyun LIU , Kan WANG

Front. Energy ›› 2021, Vol. 15 ›› Issue (4) : 974 -983.

PDF (1186KB)
Front. Energy ›› 2021, Vol. 15 ›› Issue (4) : 974 -983. DOI: 10.1007/s11708-021-0769-5
REVIEW ARTICLE
REVIEW ARTICLE

Optimization of spatial structure designs of control rod using Monte Carlo code RMC

Author information +
History +
PDF (1186KB)

Abstract

Control rod is the most important approach to control reactivity in reactors, which is currently a cluster of pins filled with boron carbide (B4C). In this case, neutrons are captured in the outer region, and thus the inner absorber is inefficient. Moreover, the lifetime of the control rod is challenged due to the high reactivity worth loss resulted from the excessive degradation of B4C in the high flux area. In this work, some control rod designs are proposed with optimized spatial structures including the spatially mixed rod, radially moderated rod, and composite control rod with small-sized pins. The control rod worth and effective absorption cross section of these designs are computed using the Monte Carlo code RMC. A long-time depletion calculation is conducted to evaluate their burnup stability. For the spatially mixed rod, rare-earth absorbers are combined with B4C in spatial structure. Compared with the homogenous B4C rod, mixed designs ensure more sufficient reactivity worth in the lifetime of the reactor. The minimum reactivity loss at the end of the cycle is only 1.8% from the dysprosium titanate rod, while the loss for pure B4C rod is nearly 12%. For the radially moderated design, a doubled neutronic efficiency is achieved when the volume ratio of moderator equals approximately 0.3, while excessive moderating may lead to the failure of control rods. The control rod with small-sized pins processes an enhanced safety performance and saves the investment in absorbers. The rod worth can be further enhanced by introducing small moderator pins, and the reactivity loss caused by the reduction of absorbers is sustainable.

Graphical abstract

Keywords

control rod / optimized spatial structure / neutronic performance / burnup stability

Cite this article

Download citation ▾
Hao LUO, Mancang LI, Shanfang HUANG, Minyun LIU, Kan WANG. Optimization of spatial structure designs of control rod using Monte Carlo code RMC. Front. Energy, 2021, 15(4): 974-983 DOI:10.1007/s11708-021-0769-5

登录浏览全文

4963

注册一个新账户 忘记密码

References

[1]

Gosset D. Absorber materials for Generation IV reactors. In: Yvon P, ed. Structural Materials for Generation IV Nuclear Reactors, Woodhead Publishing 2017

[2]

Onoue M, Kawanishi T, Carlson W R, Application of MSHIM core control strategy for Westinghouse AP1000 nuclear power plant. In: GENES4/ANP2003, Kyoto, Japan, 2003

[3]

Safarinia M, Faghihi F, Mirvakili S M, Design of emergency shutdown system for the Tehran Research Reactor, Part I: neutronics investigation. Annals of Nuclear Energy, 2017, 103: 306–314

[4]

Guo H, Garcia E, Faure B, Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation. Annals of Nuclear Energy, 2019, 129: 90–100

[5]

Park C J, Lee B, Alnajjar A T, Depletion analysis of control absorber in a small research reactor. Annals of Nuclear Energy, 2013, 60: 377–382

[6]

Hong L P. Depletion analysis on the control rod absorber of RSG gas oxide and silicide fuel cores. Atom Indonesia, 1999, 25(1): 29–46

[7]

Horn R M, Frew B D, Van Diemen P. Thermal spectrum control rod materials. In: Konings R J M, Stoller R E, eds. Comprehensive Nuclear Materials, Elsevier, 2012

[8]

Devan K, Riyas A, Alagan M, A new physics design of control safety rods for prototype fast breeder reactor. Annals of Nuclear Energy, 2008, 35(8): 1484–1491

[9]

Schunert S, Wang Y, Ortensi J, Control rod treatment for FEM based radiation transport methods. Annals of Nuclear Energy, 2019, 127: 293–302

[10]

Sakurai F, Horiguchi Y, Kobayashi S, Present status and future prospect of JRR-3 and JRR-4. Physica B, Condensed Matter, 2002, 311(1–2): 7–13

[11]

Ye C. China Advanced Research Reactor (CARR): a new reactor to be built in China for neutron scattering studies. Physica B, Condensed Matter, 1997, 241243: 48–49

[12]

Guo H, Buiron L. Innovative sodium fast reactors control rod design. In: Atoms for the Future 2018 & 4th GIF Symposium, Paris, France, 2018

[13]

Guo H, Buiron L, Kooyman T, Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators. Annals of Nuclear Energy, 2019, 132: 713–722

[14]

Guo H, Sciora P, Buiron L, Design directions of optimized reactivity control systems in sodium fast reactors. Nuclear Engineering and Design, 2019, 341: 239–247

[15]

Čerba Š, Vrban B, Lüley J, Optimization of the heterogeneous GFR 2400 control rod design. Progress in Nuclear Energy, 2017, 97: 170–181

[16]

Wang K, Li Z, She D, RMC–a Monte Carlo code for reactor core analysis. Annals of Nuclear Energy, 2015, 82: 121–129

[17]

Goorley T, James M, Booth T, Features of MCNP6. Annals of Nuclear Energy, 2016, 87: 772–783

[18]

Romano P K, Josey C J, Johnson A E, Depletion capabilities in the OpenMC Monte Carlo particle transport code. Annals of Nuclear Energy, 2021, 152: 107989

[19]

Leppänen J. Serpent–a continuous-energy Monte Carlo reactor physics burnup calculation code. VTT Technical Research Centre of Finland, 2013, available at the website of montecarlo.vtt.fi

[20]

Cetnar J, Wallenius J, Gudowski W. MCB: a continuous energy Monte Carlo burnup simulation code. In: Proceedings of the 5th International Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 1999

[21]

Okumura K, Mori T, Nakagawa M, Validation of a continuous-energy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment. Journal of Nuclear Science and Technology, 2000, 37(2): 128–138

[22]

Croff A G. ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials. Nuclear Technology, 1983, 62(3): 335–352

[23]

She D, Liu Y, Wang K, Development of burnup methods and capabilities in Monte Carlo code RMC. Annals of Nuclear Energy, 2013, 51: 289–294

[24]

She D, Liang J, Wang K, 2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code. Annals of Nuclear Energy, 2014, 64: 201–205

[25]

Wang K, Liu S, Li Z, Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model. Progress in Nuclear Energy, 2017, 98: 301–312

[26]

Blanchet D, Fontaine B. Control rod depletion in sodium-cooled fast reactor: models and impact on reactivity control. Nuclear Science and Engineering, 2014, 177(3): 260–274

[27]

Collins P E, Luciano N, Maldonado G I. Parametric study to capture the skin effect in PWR control rod depletion. Transactions of the American Nuclear Society, 2013, 119: 1327–1329

[28]

Isotalo A E, Davidson G G, Pandya T M, Flux renormalization in constant power burnup calculations. Annals of Nuclear Energy, 2016, 96: 148–157

[29]

Pusa M. Rational approximations to the matrix exponential in burnup calculations. Nuclear Science and Engineering, 2011, 169(2): 155–167

[30]

Franceschini F, Zhang B, Mayhue L, Development of a control rod depletion methodology for the Westinghouse NEXUS system. Progress in Nuclear Energy, 2013, 68: 235–242

[31]

Massih A R, Rajala T, Jernkvist L O. Analyses of pellet-cladding mechanical interaction behaviour of different ABB Atom fuel rod designs. Nuclear Engineering and Design, 1995, 156(3): 383–391

[32]

Iwasaki T, Konashi K. Development of hydride absorber for fast reactor—application of hafnium hydride to control rod of large fast reactor. Journal of Nuclear Science and Technology, 2009, 46(8): 874–882

[33]

Risovany V D, Varlashova E E, Suslov D N. Dysprosium titanate as an absorber material for control rods. Journal of Nuclear Materials, 2000, 281(1): 84–89

[34]

Pasto A E. Europium oxide as a potential LMFBR control material. Technical Report, Oak Ridge National Lab, 1973

[35]

Shoushtari M K, Kakavand T, Sadat Kiai S M, Monte Carlo simulation of a research reactor with nominal power of 7 MW to design new control safety rods. Nuclear Instruments & Methods in Physics Research, Section B, Beam Interactions with Materials and Atoms, 2010, 268(5): 519–523

[36]

Fadaei A H, Setayeshi S. Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes. Progress in Nuclear Energy, 2009, 51(1): 184–191

RIGHTS & PERMISSIONS

Higher Education Press

AI Summary AI Mindmap
PDF (1186KB)

5770

Accesses

0

Citation

Detail

Sections
Recommended

AI思维导图

/