Statistical evaluation of individual external exposure dose of outdoor worker and ambient dose rate at evacuation ordered zones after the Fukushima Daiichi Nuclear Power Station accident.

Following the accident at the Fukushima Daiichi Nuclear Power Station, evacuation orders were issued for the surrounding communities. In order to lift the evacuation order, it is necessary to determine individual external doses in the evacuated areas. The purpose of this study was to determine the quantitative relationship between individual external doses and ambient dose rates per hour as conversion coefficients. More specifically, individual external doses of Tokyo Electric Power Company Holdings employees in difficult-to-return zone were measured broadly over a long period (fiscal year 2020 to fiscal year 2022). To obtain highly accurate estimates, we used not only ambient dose rates based on airborne radiological monitoring data, but also Integrated dose rate map data that had been statistically corrected to correspond to local ambient dose rate gradients on the ground. As a result, the conversion coefficients based on the ambient dose rate map measured by airborne radiological monitoring were 0.42 for the Evacuation-Order Lifted Zones (ELZs), 0.37 for the Special Zones for Reconstruction and Rehabilitation (SZRRs), and 0.47 for the Difficult-to-Return Zones without SZRRs (DRZs). On the other hand, the conversion coefficients based on the Integrated dose rate map which is a highly accurate dose rate map based on statistical analysis of various types of monitoring that have been studied in government projects in recent years, were 0.78 for the ELZs, 0.72 for the SZRRs and 0.82 for the DRZs. Using these conversion coefficients, the individual external dose can be estimated from two representative ambient dose rate maps provided by the government.

Dose conversion coefficients for humans after oral administration of urea-14C / 中国辐射卫生

Objective To calculate the absorbed doses and conversion coefficients of various organs in humans after oral administration of urea-14C, and to provide a convenient method for evaluating the internal radiation dose caused by ingestion of urea-14C in Chinese population. Methods The Chinese reference human voxel model was imported into the FLUKA software to simulate the absorbed doses to organs under internal exposure to 14C, and to obtain the dose conversion coefficients for oral administration of urea-14C. Results The absorbed dose conversion coefficients for the stomach, colon, bladder, heart, and muscles were 0.029, 0.029, 0.32 (0.24), 0.028, and 0.029 mGy/MBq in negative cases, and 0.079, 0.078, 0.18 (0.15), 0.076, and 0.080 mGy/MBq in positive cases. The committed effective dose coefficients were 0.041 (0.037) mSv/MBq in negative cases and 0.082 (0.081) mSv/MBq in positive cases. Conclusion The dose conversion coefficients obtained in this study can provide important parameters for evaluating the absorbed dose to Chinese population after oral administration of urea-14C.

Optimal conversion coefficient from easily measurable dose to effective dose with consideration to radiation quality for posterior-anterior chest radiography.

Effective dose is sometimes used to compare medical radiation exposure to patients and natural radiation for providing explanations about radiation exposure to patients, but its calculation is lengthy and requires dedicated measuring devices. The purpose of this study was to identify the most suitable conversion coefficient for conversion of easily measurable dose to effective dose in posterior-anterior chest radiography, and to evaluate its accuracy by direct measurement. We constructed an examination environment using Monte Carlo simulation, and evaluated the variation in conversion coefficients from incident air kerma (IAK), entrance-surface air kerma (ESAK), and air kerma-area product (KAP) to effective dose when the irradiation field size and radiation quality were changed. Effective doses were also measured directly using thermoluminescence dosimeters and compared with the effective dose obtained from conversion coefficients. The KAP conversion coefficient most effectively suppressed the effect of irradiation field size, and was then used to set conversion coefficients for various half-value layers. The optimal conversion coefficient was 0.00023 [mSv/(mGy·cm2)] at 120 kVp (half-value layer = 5.5 mmAl). Evaluation of the direct measurements obtained with various radiation qualities revealed that the accuracy of the conversion coefficient was maintained at ≤ 11%. The proposed conversion coefficient can be easily calculated even in facilities that do not have equipment for measuring effective dose, and might enable the use of effective dose for providing explanations about radiation exposure to patients.

Novel method for calculating the effective dose using size-specific dose estimates conversion factors in abdomen-pelvis computed tomography.

We propose a novel method for calculating the effective dose that closely reflects the individual attenuation, utilizing two conversion coefficients. A total of 180 adult patients who underwent abdomen-pelvis computed tomography were categorized into six groups based on sex and body type. The effective dose was calculated by multiplying the dose-length product with the effective dose conversion coefficient and the size-specific dose estimate conversion factor. The effective dose calculated using a simulation-based dose calculator (WAZA-ARI) was employed as the reference value. The following values, obtained through both methods, were compared within each category: distribution of the effective dose, median effective dose, and relative difference in median effective dose across additional body mass index (BMI) categories. For male patients, no significant disparity was observed in the median effective doses calculated using the two methods. The relative differences in median effective doses across additional BMI categories ranged from - 5 to 6%. Conversely, among female patients, the median effective dose calculated using our method slightly undercut that calculated using WAZA-ARI, with relative differences ranging from - 16 to - 9%. Additionally, relative differences in median effective dose across additional BMI categories ranged from - 18 to - 7%. The median effective dose differed slightly depending on the calculation method because of the different reference phantoms applied in dose calculations. Our proposed method is sensitive to individual size and helps compute a size-specific effective dose.

Internal organ dose rate conversion coefficients of Japanese macaques to 134Cs,137Cs and 131I†.

The purpose of this study was to estimate the internal dose of radiation in Japanese macaques (aka Nihonzaru or snow monkey) due to the Fukushima nuclear power plant accident. Images of a male Japanese macaque weighing ~10 kg were acquired using a multi-slice computed tomography (CT) scan with a 64-row segment detector. The CT images were used to create voxel phantoms of the bones, bone marrow, brain, eyes, heart, lungs, stomach, liver, spleen, pancreas, kidneys, intestines, bladder, testes, thyroid and miscellaneous tissue. The Particle and Heavy Ion Transport System (PHITS) Monte Carlo code was used to calculate the internal exposure rate conversion factors for 134Cs, 137Cs and 131I isotopes for the created voxel phantoms with a statistical precision higher than 1%. The PHITS-calculated energy deposits were compared with those for rhesus monkeys. The results showed that the fractions of energy deposits for ß-radiation in different organs were almost identical between the two species. For γ-radiation, there was excellent agreement in the self-absorption rate with the approximate curve of the Japanese macaque, with an average deviation of 2%. The maximum deviation of 12% was for the kidney, which has two organs, so the error with the approximate curve is slightly larger due to the energy loss created between organs.

Pixel-Grouping G(E) Functions for Estimating Dose Rates from Unknown Source Distributions with a Position-Sensitive Detector.

Estimating accurate radiation doses when a radioactive source's location is unknown can protect workers from radiation exposure. Unfortunately, depending on a detector's shape and directional response variations, conventional G(E) function can be prone to inaccurate dose estimations. Therefore, this study estimated accurate radiation doses regardless of source distributions, using the multiple G(E) function groups (i.e., pixel-grouping G(E) functions) within a position-sensitive detector (PSD), which records the response position and energy inside the detector. Investigations revealed that, compared with the conventional G(E) function when source distributions are unknown, this study's proposed pixel-grouping G(E) functions improved dose estimation accuracy by more than 1.5 times. Furthermore, although the conventional G(E) function produced substantially larger errors in certain directions or energy ranges, the proposed pixel-grouping G(E) functions estimate doses with more uniform errors at all directions and energies. Therefore, the proposed method estimates the dose with high accuracy and provides reliable results regardless of the location and energy of the source.

Measurement of individual external doses of Tokyo Electric Power Company Holdings employees working in Fukushima Prefecture and the relationship between individual external doses and air dose rates in areas including difficult-to-return zones.

Since the Fukushima Daiichi Nuclear Power Station accident, evacuation orders have been lifted except for the difficult-to-return zones (DRZs). Within the DRZs, there has been designated a special zone for reconstruction and revitalisation (SZRR). Decontamination of the SZRR has been promoted so that evacuation orders may be lifted. Previous studies measured individual external doses in the evacuation order-lifted zones (ELZs) and other living areas where the annual additional individual external dose was overall less than approximately 5 mSv y-1. However, there have been few reports about the measurement of individual external doses in a SZRR or outside of an SZRR (O-SZRR). In SZRRs and O-SZRRs, Tokyo Electric Power Company Holdings employees work mainly outdoors. Therefore, the employees' individual external doses and air dose rates were measured in these zones from March 2020 through January 2021. Our key results were:The median (minimum to maximum) individual external doses at outdoor locations were 0.16µSv h-1(0.05-0.63µSv h-1), 0.57µSv h-1(0.15-3.92µSv h-1), and 1.36µSv h-1(0.14-11.91µSv h-1) for the ELZ, SZRR, and O-SZRR, respectively.The conversion coefficients for the air dose rate measured by airborne monitoring to individual external dose were 0.23, 0.38, and 0.50 for the ELZ, SZRR, and O-SZRR, respectively. The conversion coefficients were below 0.6, which was used in the national government model for estimating external exposure dose from air dose rate. In addition, the conversion coefficients for the SZRR and O-SZRR in air dose rates of less than 1.5µSv h-1differed from those obtained for the entire measurement range of this study.The conversion coefficient from air dose rate at a height of 1 m above ground level to individual external dose was researched across a broader and higher range of air dose rates than in the previous study (0.24-20.89µSv h-1). The conversion coefficient is confirmed to be 0.7, similar to previous studies.

CT scanner-specific organ dose coefficients generated by Monte Carlo calculation for the ICRP adult male and female reference computational phantoms.

Objective.Provide analyses of new organ dose coefficients (hereafter also referred to as normalized doses) for CT that have been developed to update the widely-utilized collection of data published 30 years ago in NRPB-SR250.Approach.In order to reflect changes in technology, and also ICRP recommendations concerning use of the computational phantoms adult male (AM) and adult female (AF), 102 series of new Monte Carlo simulations have been performed covering the range of operating conditions for 12 contemporary models of CT scanner from 4 manufacturers. Normalized doses (relative to free air on axis) have been determined for 39 organs, and for every 8 mm or 4.84 mm slab of AM and AF, respectively.Main results.Analyses of results confirm the significant influence (by up to a few tens of percent), on values of normalized organ (or contributions to effective dose (E103,phan)), for whole body exposure arising from selection of tube voltage and beam shaping filter. Use of partial (when available) rather than a Full fan beam reduced both organ and effective dose by up to 7%. Normalized doses to AF were larger than corresponding figures for AM by up to 30% for organs and by 10% forE103,phan. Additional simulations for whole body exposure have also demonstrated that: practical simplifications in the main modelling (point source, single slice thickness, neglect of patient couch and immobility of phantom arms) have sufficiently small (<5%) effect onE103,phan; mis-centring of the phantom away from the axis of rotation by 5 mm (in any direction) leads to changes in normalized organ dose andE103,phanby up to 20% and 6%, respectively; and angular tube current modulation can result in reductions by up to 35% and <15% in normalized organ dose andE103,phan, respectively, for 100% cosine variation.Significance.These analyses help advance understanding of the influence of operational scanner settings on organ dose coefficients for contemporary CT, in support of improved patient protection. The results will allow the future development of a new dose estimation tool.

[Basic Knowledge of Neutron: Physics].

Neutrons are uncharged particles and exhibit strong ability to penetrate matter. Various charged particles and gamma rays are emitted from nuclear reactions induced by neutrons passing through the matter. It is important to consider contributions of neutrons for estimating such quantities used in radiation protection as absorbed dose, equivalent dose and effective dose. In this article basic knowledge of neutron is briefly summarized concerned with physical properties of neutrons, neutron reactions, neutron sources, fluence to karma conversion coefficient, absorbed dose, equivalent dose, effective dose.

Transcriptome Analysis of Breast Muscle Reveals Pathways Related to Protein Deposition in High Feed Efficiency of Native Turkeys.

Feed efficiency is important due to the high cost of food, which accounts for about 70% of the total cost of a turkey breeding system. Native poultry are an important genetic resource in poultry breeding programs. This study aimed to conduct a global transcriptome analysis of native male turkeys which have been phenotyped for high and low feed efficiency. Feed efficiency traits were recorded during the experimental period. After slaughter, the three most efficient and three least efficient male turkeys were selected for RNA-Seq analysis. A total of 365 genes with different expressions in muscle tissue were identified between turkeys with a high feed efficiency compared to turkeys with a low feed efficiency. In the pathway analysis of up-regulated genes, major pathways included the "metabolism of glycine, serine, and threonine"; the "adipocytokine signaling pathway" and the "biosynthesis of amino acids". In the pathway analysis of down-regulated genes, the major pathways included "dorso-ventral axis formation" and "actin cytoskeleton regulation". In addition, gene set enrichment analyses were performed, which showed that high feed efficiency birds exhibit an increased expression of genes related to the biosynthesis of amino acids and low feed efficiency birds an increased expression of genes related to the immune response. Furthermore, functional analysis and protein network interaction analysis revealed that genes including GATM, PSAT1, PSPH, PHGDH, VCAM1, CD44, KRAS, SRC, CAV3, NEDD9, and PTPRQ were key genes for feed efficiency. These key genes may be good potential candidates for biomarkers of feed efficiency in genetic selection in turkeys.

Catalogue of dose rate constants for more than 400 radionuclides in terms of ambient dose H∗ and comparison of figures to ambient dose equivalent H∗(10).

In 2020, the International Commission on Radiation Units & Measurements ICRU has released Report 95 on "Operational Quantities for External Radiation Exposure". This publication introduced a new measurand, namely ambient dose H∗, as the operational quantity for external exposure to be applied in the future replacing ambient dose equivalent H∗(10). It should be noted that this change will make it necessary to adjust previously used constants and coefficients or at least to review them with regard to the new measurand. Therefore, this recommendation represents a significant cut in implementation of radiation protection systems. The revision of all previously valid factors makes it possible to develop a consistent data set. The combination of experience gained in the last decades with more extensive data sets (e.g. on the spectra of individual radionuclides) with comparatively large computing power allows the definition of optimized data collections serving as input for Monte Carlo methods. Therefore, this publication is intended to lay a suitable foundation consisting of dose rate constants for more than 400 radionuclides concerning the future measurand ambient dose H∗ and to indicate differences to values related to the ambient dose equivalent H∗(10) used nowadays.

Bias-corrected Hp(10)-to-Organ-Absorbed Dose Conversion Coefficients for the Epidemiological Study of Korean Radiation Workers.

Background: The effects of radiation on the health of radiation workers who are constantly susceptible to occupational exposure must be assessed based on an accurate and reliable reconstruction of organ-absorbed doses that can be calculated using personal dosimeter readings measured as Hp(10) and dose conversion coefficients. However, the data used in dose reconstruction contain significant biases arising from a lack of reality and could result in an inaccurate measure of organ-absorbed doses. Therefore, this study quantified the biases involved in organ dose reconstruction and calculated the bias-corrected Hp(10)-to-organ-absorbed dose coefficients for the use in epidemiological studies of Korean radiation workers. Materials and Methods: Two major biases were considered: (1) the bias in Hp(10) arising from the difference between the dosimeter calibration geometry and the actual exposure geometry and (2) the bias in air kerma-to-Hp(10) conversion coefficients resulting from geometric differences between the human body and slab phantom. The biases were quantified by implementing personal dosimeters on the slab and human phantoms coupled with Monte Carlo method and considered to calculate the bias-corrected Hp(10)-to-organ-absorbed dose conversion coefficients. Results and Discussion: The bias in Hp(10) was significant for large incident angles and low energies (e.g., 0.32 for right lateral at 218 keV), whereas the bias in dose coefficients was significant for the posterior-anterior (PA) geometry only (e.g., 0.79 at 218 keV). The bias-corrected Hp(10)-to-organ-absorbed dose conversion coefficients derived in this study were up to 3.09-fold greater than those from ICRP publications without considering the biases. Conclusion: The obtained results will aid future studies in assessing the health effects of occupational exposure of Korean radiation workers. The bias-corrected dose coefficients of this study can be used to calculate organ doses for Korean radiation workers based personal dose records.

Estimation on organ absorbed dose conversion coefficient for patients during coronary intervention procedure with Monte Carlo method / 中华放射医学与防护杂志

Objective:To calculate the conversion coefficient from dose area product (DAP) to organ absorbed dose by Monte Carlo method in order to conveniently estimate doses to patient organ during coronary intervention procedure.Methods:The Geant4 Monte Carlo simulation kit was used to calculate the organ absorbed dose conversion coefficients by simulating exposure scene.Results:The conversion coefficients used in coronary angiography (CAG) for lung, bone marrow, liver and heart were (0.283±0.068), (0.169±0.049), (0.110±0.077) and (0.080±0.032) mGy/(Gy·cm 2) for male, and (0.376±0.121), (0.192±0.056), (0.153±0.105), and (0.102±0.033) mGy/(Gy·cm 2) for female, respectively. These were similar to those in the case of percutaneous coronary intervention (PCI). The DAPs for different interventional procedures were statistically significant ( t=-6.012, P<0.05). The DAPs for difference gender groups had no statistically significant ( P>0.05). Conclusions:Conversion coefficient for organ absorbed dose has little correlation with CAG and PCI in the same sex group. Dose conversion coefficients for female group are greater than those for male group in the same procedure. Conversion coefficients from DAP to organ absorbed dose calculated with Monte Carlo method can provide convenience for rapidly estimating the organ absorbed dose to clinical patients.

Development of a secondary standard ionization chamber for environmental level ambient dose equivalent measurement.

Ambient dose equivalent is the calibration quantity and type inspection quantity of environmental and workplace radiation monitoring instrument. For other unknown radiation fields other than the reference radiation field, the method of directly measuring H*(10) by secondary standard is particularly important. In order to ensure the reliability and accuracy of the value transfer of H*(10), an energy compensated high pressure ionization chamber for environmental level measurement was developed and used as a secondary standard. Firstly, the conversion coefficients from air kerma to ambient dose equivalent of X and γ-ray reference radiation field were calculated by Monte Carlo simulation. Then, the Monte Carlo model of ionization chamber was established, the thickness and energy compensation scheme of the outer wall of the chamber high voltage electrode was determined. Finally, the performance of the chamber were studied according to the calculated conversion coefficients. The results indicate that the relative deviation between calculated conversion coefficients and recommended value of ISO 4037-3 in the range of 15 keV-1.5 MeV is within ±4%. The ionization chamber meets the energy response requirements of ISO 4037-2 in the range of 65 keV-1.25 MeV. The linearity range of ambient dose equivalent rate is 0.8 µSv/h∼11.9 mSv/h, which can be used for a directly measurement of environmental level H*(10).

A novel approach towards the calculation of dose rate constants for ambient dose equivalent H∗(10) by including low energy x-rays.

The nuclide-specific dose rate constant, formerly called gamma ray constant, is one of the most important quantities in practical radiation protection dosimetry. For radiation sources with known radionuclide composition and activity, the expected dose rates at various distances can easily be calculated with reasonable approximations. In addition, they serve as a planning basis for the design of shielding of radiation application rooms and facilities. In this study, dose rate constants were calculated using the most recent conversion coefficients and the most suitable spectral data for more than 400 radionuclides using different calculation approaches. In addition this paper provides a critical review of currently published dose rate constants for the ambient dose equivalent H∗(10).

Determination of a Pu-Be source neutron spectrum at Czech Metrology Institute.

Contrary to the radionuclide neutron sources of 252Cf and 241Am-Be type, which are most widely used for the dosimetric instrumentation calibrations, the spectral source strength and spectrum averaged fluence to dose equivalent conversion coefficients of Pu-Be source are not recommended by an international standard. This work describes the determination of those parameters for the Pu-Be source used at Czech Metrology Institute (CMI) by means of a Bonner spectrometer in combination with neutron emission rate measurement in a manganese bath.

Investigation of the effect of using radiation protective glasses on the photon fluence-to-dose conversion coefficients of eye substructures.

The use of radiation protective glasses is common in radiation-contaminated environments. However, the effect of these glasses has not yet been investigated on the fluence-to-dose conversion coefficients (DCCs). The aim of this study is to investigate the effect of five types of gamma ray protective glasses on the photon fluence-to-DCCs of different eye substructures. For this purpose, a real eye model has been used and its conversion coefficients have been calculated in the presence of five types eye protective glasses with chemical formulae of ZnO-PbO-B2O3, Bi2O3-PbO-B2O3, PbO-B2O3, PbO-BaO-Na2O-MgO-B2O3and BaO-Nb2O3-P2O5. Calculations were performed for monoenergetic photon sources, whose energy ranges from 0.02 to 10 MeV, with different polar and azimuthal angles. The results indicate that the use of radiation protective glasses has acceptable effects on reducing the fluence-to-DCCs only at low photon energies up to 500 keV. At medium energy levels up to about 1 MeV, the effect of the glasses is negligible. However, at high energies it increases the fluence-to-DCCs for sensitive parts of the eye.

Dose-Area Product-to-Effective Dose Conversion Coefficients for Pelvic Radiography Using a Monte Carlo Program.

OBJECTIVE. The purpose of this study was to determine dose-area product-to-effective dose (DAP/E) conversion coefficients for a five-view pelvic radiograph series. DAP/E conversion coefficients may be used for radiation dose optimization when designing institutional protocols for pelvic trauma evaluation. MATERIALS AND METHODS. We conducted a retrospective record review of 25 patients at a level 1 trauma center who had sustained pelvic fractures and required a five-view pelvic radiograph series during workup. E values given in International Commission on Radiological Protection Publication 103 were simulated with a PC-based Monte Carlo program in conjunction with anthropomorphic phantoms adjusted on the basis of patient height and weight. Inputs included tube voltage (in kV), tube filtration (in millimeters of aluminum), anode angle, x-ray beam collimation, geometric distances, and angle of projection for each radiograph in the series. An incident polychromatic x-ray spectrum was generated and matched to the corresponding DAP values of each radiograph, and regression analysis was performed for the DAP/E conversion coefficients. RESULTS.E was strongly correlated with DAP independent from body mass index, with a mean global DAP/E conversion coefficient of 0.0125 mSv/dGy · cm2 for all radiographs (R2 = 0.95). Mean DAP/E conversion coefficients were 0.0133, 0.0110, 0.0143, 0.0113, and 0.0101 mSv/dGy · cm2 for anteroposterior, inlet, outlet, Judet left, and Judet right views, respectively (all R2 ≥ 0.94). CONCLUSION. DAP/E conversion coefficients are provided for a five-view pelvic radiograph series to allow reliable estimation of E. Measurement of cumulative E may affirm protocol design changes for the management of pelvic trauma.

Internal exposure rate conversion coefficients and absorbed fractions of mouse for 137Cs, 134Cs and 90Sr contamination in body.

The aim of this study was to determine parameters for estimating the internal exposure of all organs in mouse experiments from the radioactivity concentration in organs. The estimation of internal exposure rate conversion coefficients and absorbed fractions for 137Cs, 134Cs and 90Sr by the Particle and Heavy Ion Transport code System (PHITS) with a voxel-based mouse phantom is presented. The geometry of the voxel phantom is constructed from computer tomography images of a mouse 9 cm in length weighing 23.9 g. The voxel-based mouse phantom has the following organs: brain, skull, heart, lungs, liver, stomach, spleen, kidneys, bladder, testis and tissue (tissue and other organs). Gamma- and beta-rays from 137Cs, 134Cs and 90Sr sources in each source organ are generated and scored for every target organ. The internal exposure rate conversion coefficients and absorbed fractions are calculated from deposition energies in each target organ from each source organ and are used to generate an internal exposure rate conversion coefficient matrix and an absorbed fraction matrix. The absorbed fractions of beta-rays in the source organs are roughly 0.5-0.8 for 137Cs and 134Cs, and the absorbed fractions of gamma-rays are <0.04 for 137Cs and <0.03 for 134Cs. The internal exposure rate conversion coefficient matrix is defined using the absorbed fractions. The calculated internal exposure rate coefficient matrix is tested under a uniform radioactivity concentration of 1 Bq/kg for 137Cs, 134Cs and 90Sr. The estimated internal exposure rates in the mouse whole body for 137Cs, 134Cs and 90Sr are 3.28 × 10-3, 2.55 × 10-3 and 1.20 × 10-2 µGy/d, respectively. These values are very similar to those for an ellipsoid frog (31.4 g) and an ellipsoid crab egg mass (12.6 g) reported in ICRP Publication 108.

[Study on assay strategy of total tritepenoid saponins in traditional Chinese medicines using total saponins from Akebiae Caulis as an example].

Due to lack of reference substances,the content of triterpenoid saponins in traditional Chinese medicines is usually characterized by colorimetric determination of total saponins. However,the specificity of colorimetric method is poor,and the determination result is not accurate enough. So,in this paper,the content determination method of total triterpenoid saponins was studied by taking Akebiae Caulis saponins as an example. The contents of three main saponin aglycones,including arjunolic acid,hederagenin and oleanolic acid,were determined by HPLC method. Referring to the content determination method of total flavonol glycosides in Ginkgo biloba leaves in the 2015 edition of Chinese Pharmacopoeia,the content of Akebiae Caulis saponins was obtained by multiplying the total content of the three above-mentioned aglycones with conversion coefficient. LC-MS/MS analysis results showed that mutongsaponin C and aponin PJIwere the two main triterpene saponins in Akebiae Caulis,and they shared the same molecular formula. So,the average value of the ratios of the molecular weight between mutongsaponin C and the three aglycones was defined as the conversion coefficient.The three aglycones were separated on an ACE Excel 3 C18-AR column( 4. 6 mm×150 mm,3 µm),and methanol-water( containing0. 04% glacial acetic acid and 0. 02% triethylamine) was used as mobile phase with gradient elution. The detection wavelength was set at 210 nm,and the flow rate was 0. 5 m L·min-1. The results showed that there was a good linearity among the ranges of 1. 053-16. 84,0. 200-3. 200 and 1. 515-24. 24 µg for arjunolic acid,hederagenin and oleanolic acid,respectively. Their average recoveries were97. 90%,97. 50% and 100. 5%,with RSD of 2. 0%,2. 9% and 2. 9%,respectively. The results of methodological investigation met the requirements of content determination. The conversion coefficient was 2. 31. This method is simple and reliable,and can be used for the determination of total triterpenoid saponins in Akebiae Caulis. The assay strategy can be used for the determination of total triterpenoid saponins in other traditional Chinese medicines.