Improvement of Radiolytic Gas Model for Criticality Accident Analysis of Nuclear Fuel Solution System

Sheng Huimin; He Junyi; Gou Junli; Shan Jianqiang; Liu Guoming

doi:10.13832/j.jnpe.2024.02.0160

Volume 45 Issue 2

Apr. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(2): 160-165

Sheng Huimin, He Junyi, Gou Junli, Shan Jianqiang, Liu Guoming. Improvement of Radiolytic Gas Model for Criticality Accident Analysis of Nuclear Fuel Solution System[J]. Nuclear Power Engineering, 2024, 45(2): 160-165. doi: 10.13832/j.jnpe.2024.02.0160

Citation:

Sheng Huimin, He Junyi, Gou Junli, Shan Jianqiang, Liu Guoming. Improvement of Radiolytic Gas Model for Criticality Accident Analysis of Nuclear Fuel Solution System[J]. Nuclear Power Engineering, 2024, 45(2): 160-165. doi: 10.13832/j.jnpe.2024.02.0160

Citation:

PDF( 2845 KB)

Improvement of Radiolytic Gas Model for Criticality Accident Analysis of Nuclear Fuel Solution System

doi: 10.13832/j.jnpe.2024.02.0160

1.
Xi’an Jiaotong University, Xi’an, 710049, China
2.
China Nuclear Power Engineering Co., Ltd., Beijing, 100840, China

Received Date: 2023-05-02
Rev Recd Date: 2023-11-17
Publish Date: 2024-04-12

Abstract

Abstract

The accurate simulation of transient criticality accident is a key factor in critical safety assessment of nuclear fuel solution system. However, the existing radiolysis gas models contain many empirical parameters, which result in significant deviations in the prediction of the power characteristics. To improve the simulation accuracy and avoid relying on the empirical parameters in the model, the radiolytic gas model needs to be improved. Based on the analysis of radiolysis gas behavior in solution and simplified assumptions, a conservation model including radiolytic gas concentration, mass per unit volume of radiolytic bubbles and number of density bubbles was established. This model was coupled with a point reactor kinetics model and a two-dimensional heat conduction model to develop a two-dimensional transient analysis code for solution systems. The code was verified with the Japanese TRACY experiment. The results show that the simulated values of the code are in good agreement with the experimental data, and the improved model can accurately simulate the power change of the solution system during critical accidents.
- Nuclear fuel solution system,
- Critical safety,
- Radiolytic gas model

FullText(HTML)

References(14)

References

[1]	MCLAUGHLIN T P, MONAHAN S P, PRUVOST N L, et al. A review of criticality accidents 2000 revision: LA-13638[R]. Los Alamos, New Mexico, USA: Los Alamos National Lab., 2000.
[2]	BASOGLU B, YAMAMOTO T, OKUNO H, et al. Development of a new simulation code for evaluation of criticality transients involving fissile solution boiling: JAERI-Data/Code 98-011[R]. lbaraki-ken, Japan: Japan Atomic Energy Research Institute, 1998.
[3]	PAIN C C, DE OLIVEIRA C R E, GODDARD A J H, et al. Non-linear space-dependent kinetics for the criticality assessment of fissile solutions[J]. Progress in Nuclear Energy, 2001, 39(1): 53-114. doi: 10.1016/S0149-1970(01)00003-8
[4]	汪量子. 溶液堆的蒙特卡罗方法物理计算模型及特性研究[D]. 北京: 清华大学,2011.
[5]	SOUTO F J, KIMPLAND R H, HEGER A S. Analysis of the effects of radiolytic-gas bubbles on the operation of solution reactors for the production of medical isotopes[J]. Nuclear Science and Engineering, 2005, 150(3): 322-335. doi: 10.13182/NSE05-A2519
[6]	WINTER G E, COOLING C M, EATON M D. A semi-empirical model of radiolytic gas bubble formation and evolution during criticality excursions in uranyl nitrate solutions for nuclear criticality safety assessment[J]. Annals of Nuclear Energy, 2022, 165: 108614. doi: 10.1016/j.anucene.2021.108614
[7]	CHURCHILL S W, CHU H H S. Correlating equations for laminar and turbulent free convection from a vertical plate[J]. International Journal of Heat and Mass Transfer, 1975, 18(11): 1323-1329. doi: 10.1016/0017-9310(75)90243-4
[8]	LANE J A, MACPHERSON H G, MASLAN F. Fluid fuel reactors[M]. Reading: Addison-Wesley, 1958: 102.
[9]	BIDWELL R M, KING L D P, WYKOFF W R. Radiolytic yields of nitrogen and hydrogen in water boilers[J]. Nuclear Science and Engineering, 1956, 1(6): 452-454. doi: 10.13182/NSE56-A18460
[10]	SPIEGLER P, BUMPUS JR C F, NORMAN A. Production of void and pressure by fission track nucleation of radiolytic gas bubbles during power bursts in a solution reactor: NAA-SR-7086[R]. Canoga Park: Atomics International, 1962.
[11]	NAKAJIMA K, YAMANE Y, MIYOSHI Y. A kinetics code for criticality accident analysis of fissile solution systems: AGNES2: JAERI-Data/Code-2002-004[R]. Tokyo: Japan Atomic Energy Research Inst., 2002.
[12]	CELATA G P, D’ANNIBALE F, DI MARCO P, et al. Measurements of rising velocity of a small bubble in a stagnant fluid in one-and two-component systems[J]. Experimental Thermal and Fluid Science, 2007, 31(6): 609-623. doi: 10.1016/j.expthermflusci.2006.06.006
[13]	KIMPLAND R H, KORNREICH D E. A two-dimensional multiregion computer model for predicting nuclear excursions in Aqueous Homogeneous Solution Assemblies[J]. Nuclear Science and Engineering, 1996, 122(2): 204-211. doi: 10.13182/NSE96-A24155
[14]	EPSTEIN P S, PLESSet M S. Erratum: on the stability of gas bubbles in liquid‐gas solutions[J]. The Journal of Chemical Physics, 1951, 19(2): 256.