• NUCLEAR TECHNIQUES
  • Vol. 48, Issue 3, 030002 (2025)
Xiaoliang CHEN*, Peng HAN, Jiyin ZHU, and Jiachen ZHU
Author Affiliations
  • Department of Reactor Engineering and Technology, China Institute of Atomic Energy, Beijing 102413, China
  • show less
    DOI: 10.11889/j.0253-3219.2025.hjs.48.240303 Cite this Article
    Xiaoliang CHEN, Peng HAN, Jiyin ZHU, Jiachen ZHU. Design and prospects of small multifunctional pool research reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(3): 030002 Copy Citation Text show less
    Core configuration of NUR reactor core[33]
    Fig. 1. Core configuration of NUR reactor core[33]
    Structural diagram of standard and control fuel assemblies[35] (color online)
    Fig. 2. Structural diagram of standard and control fuel assemblies[35] (color online)
    Top cross-sectional view of the Nur reactor[33] (color online)
    Fig. 3. Top cross-sectional view of the Nur reactor[33] (color online)
    IRR-1 reactor core structure diagram[37]
    Fig. 4. IRR-1 reactor core structure diagram[37]
    IEA-R1 reactor core structure diagram[40]
    Fig. 5. IEA-R1 reactor core structure diagram[40]
    Frame diagram of standard fuel assembly and fork-type control rod[43]
    Fig. 6. Frame diagram of standard fuel assembly and fork-type control rod[43]
    Cross-sectional view of MURR fuel assembly[49]
    Fig. 7. Cross-sectional view of MURR fuel assembly[49]
    Structural layout of MURR reactor core[49]
    Fig. 8. Structural layout of MURR reactor core[49]
    MURR reactor core cross-section[50] (color online)
    Fig. 9. MURR reactor core cross-section[50] (color online)
    TRIGA fuel UZrH component structure diagram[53] (color online)
    Fig. 10. TRIGA fuel UZrH component structure diagram[53] (color online)
    MA-R1 reactor core structure diagram[55] (color online)
    Fig. 11. MA-R1 reactor core structure diagram[55] (color online)
    Schematic diagram of involute plate fuel assembly[61]
    Fig. 12. Schematic diagram of involute plate fuel assembly[61]
    Schematic diagram of plate fuel assembly[13]
    Fig. 13. Schematic diagram of plate fuel assembly[13]
    Schematic diagram of curved plate fuel assembly[49]
    Fig. 14. Schematic diagram of curved plate fuel assembly[49]
    Schematic diagram of annular fuel element[62] (color online)
    Fig. 15. Schematic diagram of annular fuel element[62] (color online)

    名称

    Name

    国家

    Nation

    热功率

    Thermal Power / MW

    燃料类型

    (材料/几何形状)

    Fuel type

    (materials/geometry)

    富集度

    Enrichment

    密度

    Density

    / gU·cm-3

    最大热中子通量密度

    Max thermal

    Neutron flux density / n·cm-2·s-1

    应用场景/能谱

    Application scenarios/Neutron spectrum

    IRV-M2[4-6]Russia2.0UO2/棒状Rod36.00%1.40×1013
    IEA-R1Brazil5.0U3Si2/板状Plate19.90%3.001.15×1014①②③⑤⑥⑦
    RA-3[7-8]Argentina3.0U3O8/板状Plate19.75%4.808.00×1013①⑤⑦⑧
    RA-6[9-10]Argentina1.0U3Si2/板状Plate19.75%4.801.50×1013①②⑤⑦
    NURAlgeria1.0U3O8/板状Plate19.70%2.965.00×1013①②③⑤⑥
    RECH-1[11-12]Chile5.0U3Si2/板状Plate19.75%4.807.00×1013①②③⑤⑥⑧
    Apsara-U[13-14]India2.0U3Si2/板状Plate17.00%4.306.10×1013①②③⑤
    TRR[15]Iran5.0U3O8/板状Plate20.00%4.801.00×1014①②④⑤⑥⑦⑧
    IRR-1Israel5.0UAlx/板状Plate93.00%0.685.00×1013②⑤⑥
    JRTR[16-17]Jordan5.0U3Si2/板状Plate19.75%4.801.45×1014①⑤
    WWR-K[18-19]Kazakhstan6.0UO2/棒状Rod19.70%2.801.00×1012①②④⑤⑦⑧
    HOR[20]Netherland2.3U3Si2/板状Plate19.75%4.304.60×1013①③⑤
    PARR-1[21-22]Pakistan10.0U3Si2/板状Plate19.99%1.70×1014①②③⑤⑥
    RP-10[23-24]Peru10.0U3Si2/板状Plate19.75%2.301.21×1014①②③⑤⑥
    MURRUSA10.0UAlx/板状Plate93.00%1.436.00×1014①③④⑤
    RINSC[25-26]USA2.0U3Si2/板状Plate19.75%4.802.00×1013
    UMLRR[27-28]USA1.0U3Si2/板状Plate19.75%4.801.40×1013
    BTRR[29]Bengal3.0UZrH/棒状Rod19.70%7.50×1013①②③⑤
    MA-R1Morocco2.0UZrH/棒状Rod19.75%5.904.40×1013①⑤⑥
    TRIGA-MarkIII[30-31]Mexico1.0UZrH/棒状Rod20.00%6.113.00×1013①⑤
    Table 1. Summary of small pool research reactor parameters for implementing the RERTR project (including plans)

    燃料类型

    Fuel type

    优点

    Advantages

    缺点

    Disadvantages

    用途

    Applicable scenarios

    U3O8-Al

    热稳定性好;熔点高;辐照稳定性好;对包壳和冷却剂具有良好的相容性;抗腐蚀能力强

    Good thermal stability; high melting point; good irradiation stability; good compatibility with cladding and coolant; strong corrosion resistance

    相较其他金属弥散体燃料热导率小;密度低;辐照时芯块温差大

    Compared with other metal dispersion fuels, it has lower thermal conductivity, lower density and a larger temperature difference in the core during irradiation.

    适用于低燃耗、低功率、低温研究堆

    Generally suitable for low-burnup, low-power, low-temperature research reactors

    UAlx-Al

    高密度UAlx燃料内部铀的均匀性较好;抗腐蚀能力强;不易发生燃料肿胀

    The uranium inside the fuel has good uniformity, strong corrosion resistance and is less likely to swell.

    燃料铀密度相较铀硅燃料低

    The density of uranium fuel is lower than that of uranium silicon fuel.

    适用于低燃耗、低功率、低温研究堆

    Generally suitable for low-burnup, low-power, low-temperature reactors

    U3Si2-Al

    铀密度较高,且与基体的相容性较好;在破损状态下与水仅发生极轻微的反应;燃耗深

    Uranium has a high density and good compatibility with the matrix; it reacts only slightly with water in a damaged state; and it has a deep burnup.

    不适用于高功率密度研究堆;Si导热性能较金属差且后处理困难

    It is not suitable for high power density research reactors; the thermal conductivity of Si is poorer than that of metals and post-processing is difficult.

    适用于中小功率研究堆或低功率密度研究堆

    It is suitable for small and medium power research reactors or low power density research reactors,

    U-Mo

    密度和热导率较高;具备良好的辐照性能;可用于高功率研究堆;后处理简单;明显提高燃料循环周期

    It has high density and thermal conductivity, good irradiation performance, can be used in high-power research reactors, has simple post-processing, and can significantly improve the fuel cycle.

    制造技术不成熟;弥散燃料出现肿胀及燃料与基体化学反应等问题;合金燃料成型燃料板产出率较低

    The manufacturing technology is immature; the dispersed fuel has problems such as swelling and chemical reaction between the fuel and the matrix; the output rate of alloy fuel molded fuel plates is low.

    适用于高功率密度研究堆,能更好发挥燃料本身优异性能

    It is suitable for high power density research reactors and can better bring into play the excellent performance of the fuel itself.

    UZrH

    燃料安全性能较好;后处理方便;密度高;导热性好;具备良好裂变产物包容能力

    It has good fuel safety performance; easy post-processing; high density; good thermal conductivity; and good fission product containment capacity.

    容易发生包壳应变和腐蚀

    Prone to cladding strain and corrosion

    适用于低燃耗、低功率、低温研究堆

    Suitable for low-burnup, low-power, low-temperature research reactors

    Table 2. Summary of fuel type characteristics of future small research reactor

    名称(燃料富集度)

    Name (Enrichment of fuel)

    热功率

    Thermal power / MW

    最大热中子通量密度

    Max thermal neutron flux density / n·cm-2·s-1

    品质因子

    Quality factor

    IEA-R1(19.9%)51.15×10140.230
    JRTR(19.75%)51.45×10140.290
    Grenoble(93%)571.5×10150.263
    CARR(19.75%)601.0×10150.167
    ORPHEE(93%)143.0×10140.214
    PIK(90%)1004.0×10150.400
    KMRR(19.75%)305.3×10140.178
    Table 3. Quality factors of different research reactors[59-60]

    堆芯结构

    Core structure

    优点

    Advantages

    缺点

    Disadvantages

    中子阱型

    Neutron trap

    栅距大;堆初始剩余反应性较高;循环周期较长

    The larger the grid pitch, the higher the initial residual reactivity of the stack and the longer the cycle period

    堆外水池热中子、超热中子通量密度较低

    The flux density of thermal neutrons and epithermal neutrons in the external water pool is relatively low.

    反中子阱型 Anti-neutron trap

    堆芯紧凑;堆品质因子及中子通量密度高;具备堆芯中子能谱分区特点;堆慢化剂温度反应性系数具有更大的负值,安全性高

    The reactor core is compact; the reactor quality factor and neutron flux density are high; it has the characteristics of core neutron spectrum zoning; the reactor moderator has a more negative temperature reactivity coefficient and high safety.

    紧凑型堆芯栅距较小,堆芯热流密度高,较难实现堆的大功率运行

    The compact core has a small grid pitch and a high core heat flux density, making it difficult to achieve high-power operation of the reactor.

    燃料元件结构 Fuel element structure

    优点

    Advantages

    缺点

    Disadvantages

    棒状 Rod

    棒状燃料发展和使用较为成熟,在元件外壁设置绕丝,可减少棒的机械振动并提高燃料换热能力

    The development and use of rod-shaped fuel is relatively mature. Setting wire winding on the outer wall of the element can reduce the mechanical vibration of the rod and improve the fuel heat exchange capacity.

    相较其他结构,换热性能较差,对热工要求较高

    Compared with other structures, the heat exchange performance is poor and the thermal engineering requirements are higher.

    渐开线

    Involute

    可在燃料组件内部加入辐照装置或控制棒;具有较好的整体刚度、机械强度和流动阻力特性;易于堆芯紧凑,具备双流道,适合大功率运行

    Irradiation devices or control rods can be added inside the fuel assembly; it has good overall stiffness, mechanical strength and flow resistance characteristics; Easy to compact the reactor core, it has dual flow channels, suitable for high-power operation.

    不易于进行大尺寸和多数目的孔道布置;渐开线燃料组件实施整体换料,出堆平均燃耗较浅

    It is not easy to arrange large-size and multi-purpose channels. The involute fuel assembly is replaced as a whole, and the average fuel out of the stack is shallow.

    平板状

    Flate

    表面积/体积比较大,导热性能好;具备良好的机械性能和热稳定性;结构灵活,可布置大量孔道

    It has a large surface area/volume ratio and good thermal conductivity; Good mechanical properties; Structure is flexible and a large number of channels can be arranged.

    板状燃料元件间距小,容易出现冷却剂流道堵塞事故

    The spacing between plate-shaped fuel elements is small and the coolant flow path is prone to clogging accidents.

    曲板状

    Curved plate

    表面积/体积比较大,导热性能较好;易于堆芯紧凑,减小堆芯体积 It has a large surface area/volume ratio, good thermal conductivity. It is easy to compact the core and reduce the core volume.板状燃料元件间距小,容易出现冷却剂流道堵塞事故 The spacing between plate-shaped fuel elements is small and the coolant flow path is prone to clogging accidents.

    环形燃料

    Annular fuel

    具备较大的表面积/体积比,导热性能较好,能大幅降低燃料峰值温度,适用于高性能研究堆

    It has a large surface area/volume ratio, good thermal conductivity, can reduce the peak fuel temperature, and is suitable for high-performance research reactors.

    环形燃料元件研发面对各种工程安全问题

    The development of annular fuel elements faces various engineering safety issues

    Table 4. Summary of fuel type characteristics of future small research reactor

    应用分类

    Application classification

    应用场景

    Application scenarios

    能谱

    Neutron spectrum

    中子通量密度

    Neutron flux density / n·cm-2·s-1

    孔道直径

    Channel diameter / cm

    同位素生产Mo-99E<0.625 eV1.0~1.5×10145.2
    Isotope productionIr-192 (Industry)E<0.625 eV1.0~1.5×10145.2
    Ir-192 (Medical)/Lu-177E<0.625 eV>2.0×10145.2

    材料、燃料考验

    Material and fuel test

    反应堆结构材料

    Reactor structural materials

    E>0.1 MeV>3.0×10145
    燃料板Fuel plateE<0.625 eV>1.0×1014

    压力容器

    Pressure vessel

    E>0.1 MeV1.0×10145

    水平孔道

    Horizontal tunnel

    冷中子束流Cold neutron beamE<0.01 MeV>1.0×109

    热中子束流

    Thermal neutron beam

    E<0.1 MeV>1.0×109
    其他应用NTDE<0.625 eV1.0~4.0×101310~30
    Other applicationNAA (Thermal)E<0.625 eV1.0~20×10133~5
    热中子散射Thermal neutron scatteringE<0.625 eV1.0×1015
    热柱Hot columnE<0.625 eV

    >1.0×1015

    热中子份额

    Thermal neutron share>90%

    BNCT0.625 eV<E<0.1 MeV

    超热中子Epithermal neutron>1.0×1010

    快中子成分Fast neutron component<2.0×10-13 Gycm-2·n-1

    γ射线成分Gamma ray components <2.0×10-13Gycm-2·n-1

    热中子通量占比Thermal neutron flux proportion<0.05

    中子束斑直径

    Neutron beam spot diameter

    12~14

    Table 5. Research reactor application scenarios and reactor performance requirements[9, 63]
    Xiaoliang CHEN, Peng HAN, Jiyin ZHU, Jiachen ZHU. Design and prospects of small multifunctional pool research reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(3): 030002
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