Journal of Radiological Protection最新文献

{"title":"Numerical modelling of the transport and impact of¹³⁷Cs and¹³¹I on the Meuse-Campine Canals after a potential nuclear accident.","authors":"Amit Ravindra Patil, Fabricio Fiengo Perez, Jonathan Lambrechts, Eric Deleersnijder","doi":"10.1088/1361-6498/adc1db","DOIUrl":"10.1088/1361-6498/adc1db","url":null,"abstract":"<p><p>The Meuse River in Belgium can be impacted by the two nuclear power plants (Tihange and Chooz) located on its banks. Nuclear disasters such as the Fukushima and Chernobyl accidents have illustrated the risks associated with the civilian nuclear industry. In such situations, predictive models become crucial for developing environmental strategies to minimize the potential impact. In this study, we use the SLIM model to simulate the transport of¹³⁷Cs and¹³¹I in the Meuse River system in Belgium. Several hypothetical accidental scenarios are considered for the radionuclide releases based on past nuclear accidents. The simulated radioactive distributions are then used to estimate the individual dose for drinking water. The radionuclide transport in the Meuse River is within days. While the higher peak concentration in the Meuse River results in higher individual dose. The Albert canal being the largest channel among the Campine canals; therefore, the radioactive plume stays over a month. The estimated individual doses for releases from Chooz Nuclear power plant near Tailfer reached 0.2 mSv within three days. Although it takes days, the doses in the Albert Canal reach values up to 0.46 mSv at Haccourt (hypothetical locations). The water extraction points in Herentals, located downstream of the canal, has a negligible individual dose estimation. Higher doses are the consequence of¹³¹I than¹³⁷Cs due to the larger release scenario.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143659580","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Occupational exposure and radiological risks from x-ray baggage screening in eastern China.","authors":"Peng Dang, Ziya Feng, Xiaoyong Yang, Xingjiang Cao, Xiaolei Shen, Jin Wang","doi":"10.1088/1361-6498/adc014","DOIUrl":"10.1088/1361-6498/adc014","url":null,"abstract":"<p><p>The occupational personnel of x-ray baggage screening may experience chronic or abnormal radiation exposure. However, their exposure hazards and individual protections remain ambiguous, especially for some new applications and key positions. In this work, exposure levels were analysed through on-site inspection and Monte Carlo simulation. The effective dose and radiological risk were estimated using the International Commission on Radiological Protection, United Nations Scientific Committee on the Effects of Atomic Radiation, and Biologic Effects of Ionizing Radiation VII risk models. The results show that the workplace dose rate could be controlled at a low level under normal use, with a mean value of 0.21<i>µ</i>Sv·h^-1from the survey. However, it is necessary to strengthen radiation protection for some new applications, such as workshops, whose maximum dose rate could reach up to 2.07<i>µ</i>Sv·h^-1. Additionally, the maximum leakage dose could greatly exceed dose limits under abnormal working conditions. Furthermore, the radiological risk to maintenance and commissioning should be given more attention, as they may be exposed to risks of up to 1.3 × 10^-3% during one work shift. This result is beneficial to deepen the understanding of occupational exposure risks, which could guide individual protection and workplace management.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143626702","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimizing Ca-DTPA/Zn-DTPA therapy for internal decorporation: transitioning from intravenous to oral route with insights on safety and toxicity.","authors":"Nidhi Sandal, Riya Mahar, Pooja Sharma","doi":"10.1088/1361-6498/adc013","DOIUrl":"10.1088/1361-6498/adc013","url":null,"abstract":"<p><p>Ca-DTPA and Zn-DTPA are the decorporating agents approved by the USFDA for removing plutonium, americium, or curium from the subjects known or suspected to be contaminated with these radionuclides. Ca-DTPA and Zn-DTPA are well-known chelating agents with a strong affinity for many bivalent, trivalent, and certain tetravalent metal ions, including plutonium (Pu⁺⁴) and thorium (Th⁺⁴). The major problem associated with Ca-DTPA and Zn-DTPA therapy is that the only approved route of administration is intravenous or inhalation due to its extremely poor bioavailability. Both these drugs belong to BCS class III drugs with high solubility and low permeability. Researchers are exploring various approaches to make these drugs bioavailable via alternate routes, especially the oral route. This will enable pre-hospital care, better patient compliance, and minimize its clinically significant side effect of electrolyte imbalance. The present paper highlights the practical feasibility and challenges of establishing an oral route for delivering Ca-DTPA and Zn-DTPA with the research around it. Also, the paper highlights the importance of establishing an oral dose and the dosing schedule for Ca-DTPA and Zn-DTPA before plunging into its formulation development. These advancements underline the potential of orally administered chelating agents and alternative delivery methods in addressing the limitations of current intravenous formulations and improving accessibility and patient outcomes.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143626703","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Reducing risks through regulatory cooperation: a review of bilateral regulatory cooperation between the Norwegian Radiation and Nuclear Safety Authority and corresponding authorities in countries of the former Soviet Union.","authors":"Malgorzata Sneve, Graham Smith","doi":"10.1088/1361-6498/adbe82","DOIUrl":"10.1088/1361-6498/adbe82","url":null,"abstract":"<p><p>The Norwegian government has maintained a plan of action on nuclear safety and security for over 25 years. The need for such a plan grew from extensive nuclear activities during the Cold War, both civil and military, that led eventually to significant amounts of radioactive waste (RW) and nuclear material being stored in unsafe conditions in Northwest Russia. As part of the program to implement the plan of action, the Norwegian Radiation and Nuclear Safety Authority has maintained a program of bilateral regulatory cooperation with corresponding authorities in countries of the former Soviet Union for over 25 years. This paper reviews the background to that regulatory program, identifies the main radiologically hazardous objects and the related regulatory challenges, and then documents how bilateral cooperation has contributed to the substantial progress made in risk reduction. The review then considers how bilateral work has contributed to and benefitted from sharing results and experience with international partners and draws conclusions and lessons for future work. The primary conclusion is that bilateral regulatory cooperation has supported reduction of radiation and nuclear risks at a range of complex legacy sites and facilities in countries of the former Soviet Union. Key to this process has been a clear strategy to help build and maintain an up-to-date, robust and independent regulatory process. Only with well-coordinated regulatory bodies with clear responsibilities and functions is it possible to address the diverse threats effectively. Among the most radiologically significant sites and facilities where risk has been significantly reduced or eliminated are the LEPSE spent fuel and RW storage vessel, the site for temporary storage for spent fuel and RW at Andreeva Bay, and the very large radio-isotope thermo-electric generators sources previously used in navigational devices all across the Russian arctic coastline. Noting the clear potential for transboundary impacts, this represents a substantial regional benefit. Following the full-scale invasion of Ukraine by the Russian Federation in February 2022, the bilateral cooperation activities with Russian authorities ceased. Using the successfully developed regulatory working methods and experience gained in Russia, substantial regulatory enhancement has also been achieved in countries of Central Asia and Ukraine, commencing in 2008 and 2014 respectively. Continuing such support in Ukraine, in the face of new regulatory challenges arising due to the full-scale Russian invasion, remains a high priority for the DSA within the Norwegian Nansen program.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143598232","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Harmonization of practice of release of patients after radiopharmaceutical therapy.","authors":"Larisa Chipiga, Anastasia Likhacheva, Aleksandr Vodovatov, Irina Zvonova, Andrey Stanzhevskiy, Daria Vazhenina, Dmitrii Maystrenko","doi":"10.1088/1361-6498/adba70","DOIUrl":"10.1088/1361-6498/adba70","url":null,"abstract":"<p><p>The implementation of novel therapeutic radiopharmaceuticals requires developing, updating, and harmonizing requirements for radiation safety in radiopharmaceutical therapy (RPT). Public exposure from patients with administered radiopharmaceuticals and biological radioactive waste management have been identified as the main problems in RPT. The aim of our study was to compare different approaches to the development of patient release criteria after RPT with different radiopharmaceuticals, considering radiation exposure of members of the public in transport, biological elimination of radionuclides from a patient's body, and the generation of biological waste. The study was performed for the following radiopharmaceuticals:¹⁷⁷Lu-PSMA-617,¹⁷⁷Lu-DOTATATE, Na¹³¹I,¹³¹I-mIBG, and¹⁵³Sm-oxabifor. Two base approaches to patient release criteria were considered. The first approach is based on the radioactive decay of radionuclides and is divided into two groups: considering one radiopharmaceutical administration and considering several radiopharmaceutical administrations per course. The second approach is based on the radioactive decay of radionuclides and biological elimination of radiopharmaceuticals from the patient's body (effective half-life) and is divided into groups based on 1 and 5 mSv dose constraints per course. The ffective dose rates from patients and sewage tanks to passengers and staff on public transport were estimated for various scenarios of patients traveling after RPT. The results demonstrated that the radiation safety of members of the public in transport should be considered when establishing the release criteria of patients after RPT. Based on the results, it is recommended to follow the approach based on the radioactive decay of radionuclides and dose constraints to members of the public in contact with patients of 1 mSv per radiopharmaceutical administration, and keep patients in the nuclear medicine department after radiopharmaceutical administration for at least 4-6 h. The patient release criteria defined according to this approach comply with patient release criteria used in different countries, and allow the radiation safety of the public to be maintained.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143517187","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comparison of radiation-related cancer risk against baseline cancer rates in 33 countries using disability-adjusted life years (DALYs), lifetime incidence risk and lifetime mortality risks.","authors":"Jun Hirouchi, Ikuo Kujiraoka, Shogo Takahara, Momo Takada, Thierry Schneider, Michiaki Kai","doi":"10.1088/1361-6498/adba6f","DOIUrl":"10.1088/1361-6498/adba6f","url":null,"abstract":"<p><p>A risk indicator that allows for the comparison of risks caused by different factors is highly useful for enhancing public understanding. The International Commission on Radiological Protection developed the concept of 'detriment' to quantify radiation-related health effects at low doses. However, the detriment is specific to the radiation field and cannot be simply compared with other risks. In this study, the disability-adjusted life years (DALYs), lifetime incidence risk, and lifetime mortality risk due to radiation exposure were compared among 33 countries. These risk indicators were calculated for all solid cancers, colon cancer, lung cancer, breast cancer, thyroid cancer, and leukaemia. The values of risk indicators for all solid cancers differed by a factor of 1.5-2.0 for male and 1.2-1.5 for female among countries, with higher values observed in countries with a higher socio-demographic index. The ratios of radiation risk indicators to the baseline indicators (R/B ratios) were 10%-15% for male and 15%-25% for female under chronic exposure to 20 mSv yr^-1radiation from the age of 18 to 64 years, and 1.0%-1.5% for male and 1.5%-2.5% for female under chronic exposure to 1 mSv yr^-1radiation over a lifetime. In particular, the R/B ratios under chronic exposure to 1 mSv yr^-1radiation were smaller than the variation in the baseline risk indicators across countries. The impact of different countries and stages of disability weight of DALYs was small. Note that estimates of DALYs for less lethal thyroid cancers were subject to greater uncertainty. This study indicated that DALYs should be noted as an alternative indicator to the radiation detriments when discussing the tolerability of radiation and communicating with the society.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143517182","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Construction of tetrahedral mesh phantom for Chinese women of childbearing age.","authors":"Haowei Zhang, Tiangui Zhang, Xiaole Li, Ying Liu, Li Sun","doi":"10.1088/1361-6498/adaecd","DOIUrl":"10.1088/1361-6498/adaecd","url":null,"abstract":"<p><p>Although the boundary representation (BREP) method creates detailed surface phantoms of Chinese women of childbearing age, these phantoms cannot be directly used in Monte Carlo simulations. They must first be converted into voxel phantoms, a process that may diminish some of the inherent advantages of the surface phantoms. Therefore, the aim of this study is to construct a tetrahedral mesh (TM) phantom of Chinese women of childbearing age based on the BREP phantom, incorporating micron-level structural refinements to certain organ tissues while maintaining the original model's structure. This TM phantom can be directly implemented into Monte Carlo codes to calculate the absorbed dose at different photon energies, demonstrating that both the structure and position of organ tissues affect the radiation dose. By achieving more accurate dose assessments, we can optimize radiation protection measures and reduce the potential risks to women of childbearing age.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143054027","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effects of different accident scenarios and sites on the reduction factor used for expressing sheltering effectiveness.","authors":"Jun Hirouchi, Masatoshi Watanabe, Naho Hayashi, Azusa Nagakubo, Shogo Takahara","doi":"10.1088/1361-6498/adba6e","DOIUrl":"10.1088/1361-6498/adba6e","url":null,"abstract":"<p><p>Public living in areas contaminated by nuclear accidents is exposed to radiation in the early phase and over the long term. Even under similar accident scenarios, radiation doses and sheltering effectiveness, which is one of the protective measures, depend on meteorological conditions and the surrounding environment. Radiation doses and sheltering effectiveness in the early phase of nuclear accidents are crucial information for the public as well as national and local governments planning a nuclear emergency preparedness. In this study, we assessed radiation doses and sheltering effectiveness at sites with nuclear facilities in Japan using the Off-Site Consequence Analysis code for Atmospheric Release accidents, which is one of the level-3 probabilistic risk assessment codes, for five accident scenarios: three scenarios from past severe accident studies, a scenario defined by the Nuclear Regulation Authority in Japan, and a scenario corresponding to the Fukushima-Daiichi Nuclear Power Station accident. The sheltering effectiveness differed by up to approximately 50% among the accident scenarios at the same sites and by approximately 20%-50% among sites under the same accident scenario. Differences in the radionuclide composition among the accident scenarios and the differences in wind speeds among the sites primarily caused these differences in sheltering effectiveness.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143517184","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Chronic inflammation in a radium dial painter cohort: elevated neutrophil to lymphocyte ratio and radiation-induced hearing loss.","authors":"R E Goans, L T Dauer, C J Iddins, M Mumma, S L McComish, S Y Tolmachev","doi":"10.1088/1361-6498/adac69","DOIUrl":"10.1088/1361-6498/adac69","url":null,"abstract":"<p><p>The radium dial painters (RDPs) are a well-described group of predominantly young women who incidentally ingested²²⁶Ra and²²⁸Ra as they painted luminescent watch dials in the first part of the twentieth century. In 1974 pathologist Dr William D. Sharpe published complete clinical and autopsy results for 42 former RDPs evaluated in the New Jersey Radium Research Project. This was an important paper due to the completeness of the observations. Surprisingly, in this study, clinicians noted a 35.5% incidence of hearing loss, both conductive and mixed etiologies. Since the 1974 publication, there has developed a considerable literature on radiation-induced hearing loss in patients undergoing radiotherapy for head and neck cancers. It is expected that hearing loss would also be associated with systemic inflammation. Recently, the neutrophil to lymphocyte ratio (NLR) has been shown in many cancer and non-cancer studies to be a nonspecific marker of inflammation. In prior collaborative efforts with the United States Transuranium and Uranium Registries and with the NCRP Million Person Study, it has been possible to evaluate NLR from medical records of a cohort of 166 former RDPs previously evaluated at Argonne National Laboratory. In addition, NLR was available in historic medical records of the sarcoma and nasopharyngeal cancer patients described in Rowland's summary of the Argonne studies. Using elevation of the NLR as a non-specific marker of inflammation, chronic inflammation has been observed in all cohorts with significant dose. The RDP cohort has had a unique exposure to radium, but the incidence of radiation-induced hearing loss here is uncertain. Due to cosmic radiation dose to astronauts in space flight, there is a significant interest in high LET radiation dose to the brain, including the auditory system. This paper should be considered as hypothesis generating-that high LET radiation dose to the brain and auditory system may induce hearing loss.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143015118","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Chronic bronchitis and bronchial asthma: the impact of chronic occupational radiation exposure on incidence and mortality of Mayak nuclear workers.","authors":"Galina V Zhuntova, Tamara V Azizova, Maria V Bannikova","doi":"10.1088/1361-6498/ad90ee","DOIUrl":"10.1088/1361-6498/ad90ee","url":null,"abstract":"<p><p>The information about the radiation risk of non-cancer respiratory diseases is inconsistent and mainly corresponds to mortality. Previously, the cohort of workers employed at the first Russian nuclear facility Mayak Production Association who were occupationally exposed to gamma rays (externally) and to alpha-active plutonium aerosols (internally) over prolonged periods demonstrated an increased risk of chronic bronchitis (CB) incidence. Within this retrospective cohort study, we performed analyses of incidence of and mortality from CB and bronchial asthma (BA) using improved estimates of radiation doses provided by the 'Mayak Worker Dosimetry System (MWDS)-2013'. The cohort included 22 377 individuals hired in 1948-1982, and its follow-up was extended by 10 years (to the end of 2018). The excess relative risk of CB incidence per unit of accumulated lung-absorbed radiation dose (ERR/Gy) and the 95% confidence interval (95% CI) were: with the 0 year lag, ERR/Gy was 0.07 (95% CI -0.01, 0.17) for gamma exposure and 0.36 (95% CI 0.13, 0.68) for alpha exposure; with the 10 year lag, ERR/Gy was 0.15 (95% CI 0.04, 0.30) for gamma exposure and 0.54 (95% CI 0.19, 1.03) for alpha exposure. No strong evidence was found indicating that gamma and alpha exposure considerably impacted the risk of mortality from CB. The study confirmed the significant positive linear association of the CB incidence risk with gamma and alpha radiation doses from occupational chronic external and internal exposure. However, the estimates of ERR/Gy of alpha particles from internal exposure appeared to be almost three times lower than those based on the MWDS-2008 doses. The observed inconsistency requires further clarification. As for BA in Mayak workers, no association was demonstrated in the incidence and mortality risks with occupational gamma and alpha radiation exposure.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142631552","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}