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All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Estimating Public Dose Along Hypothetical Spent Nuclear Fuel Transportation Routes

In the future, it will be necessary to transport large quantities of spent nuclear fuel (SNF) from nuclear power plant sites to an interim storage facility (ISF) or a repository when such a facility is available. Because it is impossible to shield all of the radiation from this material, the general public will receive a very small, but quantifiable, dose from this transportation campaign. This paper describes the estimated collective effective radiation dose to the public due to SNF shipments under routine conditions and compares the estimated dose figures to the natural background radiation dose. To determine the estimated collective effective dose to the public, this analysis uses the US Department of Energy's (DOE) Stakeholder Tool for Assessing Radioactive Transportation (START), a geographic information system (GIS) routing tool, and a set of unit dose factors (UDFs) which were developed to calculate the estimated dose to the public along transportation routes. The estimated doses of radiation to which the public would be exposed during shipments of SNF is expected to be a consideration, along with many other factors, when making routing decisions. In all cases studied in this paper, estimated doses to the public will be orders of magnitude lower than the natural background radiation dose and will meet all US federal regulatory requirements for radiation dose/exposure to members of the public. The sample routes analyzed in this paper are expected to be representative of future SNF shipment routes in terms of length and mode of transportation, although they do not represent actual routes or destinations. This paper considers four routes from two shutdown reactor sites to two destinations. It must be noted that the specified origin sites are not necessarily the first sites under consideration for a de-inventory process. Further, the destination sites reviewed in this report are only to illustrate estimated dose figures along different routes and should not be taken as potential sites for an ISF or repository. For illustrative purposes only, the shortest distance rail route was found between each origin and destination point, and the collective effective dose to the public from the SNF cask was estimated along each route. This paper is not intended to make recommendations for routing decisions, but rather is intended to inform further discussion about the transportation of SNF and other radioactive materials.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Dose estimation to a worker hand from depleted uranium handling - 25471

This work is a study of the dose to a hand from a depleted uranium (DU) slab. This research evaluates and compares the effective dose and localized skin-absorbed dose from handling depleted uranium. The analysis includes photons, neutrons, and beta particles emanating from depleted Uranium aged to 30 years. Although partial effective dose rates are small, the electron localized skin-absorbed dose rate is significant. These results may be used to check compliance with safety regulations, policies and procedures at the Los Alamos National Laboratory, and to build recommendations for the safe handling of depleted Uranium samples. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

PF-06409577 activates AMPK signaling to protect retinal pigment epithelium cells from UV radiation

Highlights: • PF-06409577 protects retinal pigment epithelium (RPE) cells from ultra-violet radiation (UVR). • PF-06409577 activates AMPK signaling in RPE cells. • AMPK activation mediates PF-06409577-induced RPE cytoprotection against UVR. • PF-06409577 activates NADPH and Nrf2 signaling in RPE cells. • PF-06409577 inhibits UVR-induced oxidative injury in RPE cells. Ultra-violet (UV) radiation (UVR) to human retinas induces oxidative injury to the resident retinal pigment epithelium (RPE) cells. PF-06409577 a novel, potent and direct AMP-activated protein kinase (AMPK) activator. In ARPE-19 cells and primary murine RPE cells, PF-06409577 significantly inhibited UVR-induced viability reduction, cell death and apoptosis. PF-06409577 activated AMPK signaling in RPE cells by increasing AMPKα1-acetyl-CoA carboxylase phosphorylation and AMPK activity. AMPK inhibition, by AMPKα1-shRNA, -CRISPR/Cas9 knockout or -T172A dominant negative mutation, almost abolished PF-06409577-induced RPE cytoprotection against UVR. PF-06409577 enhanced nicotinamide adenine dinucleotide phosphate (NADPH) activity and expression levels of Nrf2-dependent genes in RPE cells. Furthermore, UVR-induced reactive oxygen species (ROS) production, lipid peroxidation and DNA damage were largely inhibited by the AMPK activator. In summary, PF-06409577 inhibits UVR-induced oxidative stress and RPE cell death by activating AMPK signaling.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2016

WE-F-209-01: Radiation Safety Surveys in Diagnostic Imaging

Over the past few years, numerous Accreditation Bodies, Regulatory Agencies, and State Regulations have implemented requirements for Radiation Safety Surveys following installation or modification to x-ray rooms. The objective of this session is to review best practices in performing radiation safety surveys for both Therapy and Diagnostic installations, as well as a review of appropriate survey instruments. This session will be appropriate for both therapy and imaging physicists who are looking to increase their working knowledge of radiation safety surveys. Learning Objectives: Identify Appropriate Survey Meters for Radiation Safety Surveys Develop best practices for Radiation Safety Surveys for Therapy units that include common areas of concern. Develop best practices for Radiation Safety Surveys of Diagnostic and Nuclear Medicine rooms. Identify acceptable dose levels and the factors that affect the calculations associated with performing Radiation Safety Surveys.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2016

WE-F-209-02: Radiation Safety Surveys of Linear Accelerators

Over the past few years, numerous Accreditation Bodies, Regulatory Agencies, and State Regulations have implemented requirements for Radiation Safety Surveys following installation or modification to x-ray rooms. The objective of this session is to review best practices in performing radiation safety surveys for both Therapy and Diagnostic installations, as well as a review of appropriate survey instruments. This session will be appropriate for both therapy and imaging physicists who are looking to increase their working knowledge of radiation safety surveys. Learning Objectives: Identify Appropriate Survey Meters for Radiation Safety Surveys Develop best practices for Radiation Safety Surveys for Therapy units that include common areas of concern. Develop best practices for Radiation Safety Surveys of Diagnostic and Nuclear Medicine rooms. Identify acceptable dose levels and the factors that affect the calculations associated with performing Radiation Safety Surveys.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2013

Testing for characterization of the materials from radiological point of view

The nuclear techniques and materials are now used in a large number of applications, both in medicine and industry. Due to this fact, new materials are needed in order to assure the radiological protection of the personnel involved in these activities. But, finally, all these materials have to be tested for some specific parameters, in order to prove that they are adequate for the purposed for which they were created. One of the important parameters of the materials used for the radiological protection is the attenuation coefficient. The attenuation coefficient of the ionizing radiation composed by particles without electrical charge (X,γ-ray and neutron) is the most important parameter for the materials used for the shielding of these ionizing radiation. This paper deals with the experimental methods developed for the determination of the attenuation of fast and thermal neutrons. These experimental methods, involved the use of Am-Be source and U-120 Cyclotron of IFIN-HH. For the tests which were done at the U-120 Cyclotron, a number of experiments had to be performed, in order to establish the irradiation geometry and the dose equivalent rates in front of and behind the material samples. The experimental results obtained for samples of several materials, confirmed the methods as adequate for the aim of the test.

36 MATERIALS SCIENCE↗
DOE OSTI2015

MO-DE-BRA-02: From Teaching to Learning: Systems-Based-Practice and Practice-Based-Learning Innovations in Medical Physics Education Programs

Purpose: The increasing complexity in the field of radiation medicine and concomitant rise in patient safety concerns call for enhanced systems-level training for future medical physicists and thus commensurate innovations in existing educational program curricula. In this work we report on the introduction of three learning opportunities to augment medical physics educational programs towards building systems-based practice and practice-based learning competencies. Methods: All initiatives were introduced for senior -level graduate students and physics residents in an institution with a newly established medical-physics graduate program and therapeutic-physics residency program. The first, centered on incident learning, was based on a spreadsheet tool that incorporated the reporting structure of the Radiation Oncology-incident Learning System (ROILS), included 120 narratives of published incidents and enabled inter-rater variability calculations. The second, centered on best-practices, was a zero-credit seminar course, where students summarized select presentations from the AAPM virtual library on a weekly basis and moderated class discussions using a point/counterpoint approach. Presentation styles were critiqued. The third; centered on learning-by-teaching, required physics residents to regularly explain fundamental concepts in radiological physics from standard textbooks to board certified physics faculty members. Results: Use of the incident-learning system spreadsheet provided a platform to recast known accidents into the framework of ROILS, thereby increasing awareness of factors contributing to unsafe practice and appreciation for inter-rater variability. The seminar course enhanced awareness of best practices, the effectiveness of presentation styles and encouraged critical thinking. The learn-by-teaching rotation allowed residents to stay abreast of and deepen their knowledge of relevant subjects. Conclusion: The incorporation of systems-driven initiatives broadens comprehension of the wider systems context of medical physics, enhances awareness of resources for innovation, communication and sustained learning while maintaining a metric-driven focus on patient safety within the formative phase of student careers. The initiatives were well-received, feasible, and utilized available or shared-resources translatable across educational programs.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2015

WE-G-BRA-03: Developing a Culture of Patient Safety Utilizing the National Radiation Oncology Incident Learning System (ROILS)

Purpose: To transition from an in-house incident reporting system to a ROILS standards system with the intent to develop a safety focused culture in the Department and enroll in ROILS. Methods: Since the AAPM Safety Summit (2010) several safety and reporting systems have been implemented within the Department. Specific checklists and SBAR reporting systems were introduced. However, the active learning component was lost due to reporting being viewed with distrust and possible retribution.To Facilitate introducing ROILS each leader in the Department received a copy of the ROILS participation guide. Four specific tasks were assigned to each leader: develop a reporting tree, begin the ROILS based system, facilitate adopting ROILS Terminology, and educate the staff on expectations of safety culture. Next, the ROILS questions were broken down into area specific questions (10–15) per departmental area. Excel spreadsheets were developed for each area and setup for error reporting entries. The Role of the Process Improvement Committee (PI) has been modified to review and make recommendations based on the ROILS entries. Results: The ROILS based Reporting has been in place for 4 months. To date 64 reports have been entered. Since the adoption of ROILS the reporting of incidents has increased from 2/month to 18/month on average. Three reports had a dosimetric effect on the patient (<5%) dose variance. The large majority of entries have been Characterized as Processes not followed or not sure how to Characterize, and Human Behavior. Conclusion: The majority of errors are typo’s that create confusion. The introduction of the ROILS standards has provided a platform for making changes to policies that increase patient safety. The goal is to develop a culture that sees reporting at a national level as a safe and effective way to improve our safety, and to dynamically learn from other institutions reporting.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2016

SU-B-BRA-05: Panel Member

In the current rapidly changing Healthcare environment, many groups are competing for limited resources. How can medical physicists position themselves to be a relevant stakeholder in the discussion of how those resources are allocated Our value goes beyond what can be shown in a business plan and is heavily involved with safety and quality. Three areas will be explored: What is our value? Who needs to receive that message? How do we communicate that message? To help frame the discussion in terms of how other stakeholders may view the value of medical physicists, a physician and an administrator will present their perspective. Lastly, a multidisciplinary panel will present real life examples of strategies that can be utilized today to establish the value of medical physicists. The presentation of these examples will lead into an interactive question and answer time. V. Willcut, I work for Elekta. There was no research associated with this talk.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2019

V.A.A.R.E.D. Measurements for Air Sampler Filters

VAARED is described as 1. Viscous Flow and Pressure; 2. Alpha FWHM of 218 Po peak; 3. Absorption, self (mass loading); 4. Radon Progeny Collection (natural aerosol); 5. Efficiency (Aerosol Collection); and, 6. Depth (Burial of non-natural aerosol).

61 RADIATION PROTECTION AND DOSIMETRY↗
NASA NTRS1991

Foundation, excavation and radiation shielding concepts for a 16-m large lunar telescope

NASA is considering a 16-m diameter optical telescope on the moon as a part of the Space Exploration Initiative. Fundamental concepts of engineering activities on the moon and how they can be applied to the establishment of a 16-m large lunar telescope (LLT) are discussed. These fundamental concepts include the engineering response of lunar soils and how they affect construction activities, namely, drilling, blasting, ripping, digging and compaction. A mirror support structure and foundation design concept is proposed. The foundation considered is a multiple contact points spud-can type footing. It does not appear that a deep foundation or the presence of bedrock is required to achieve the telescope foundation stiffness. The LLT system will include a regolith covered housing, the size of a small room, which will contain sensitive electronic equipment including charge coupled devices which need protection from cosmic radiation effects. A brief discussion is made on radiation, radiation transport and radiation effects on electronics and on humans. Radiation protection techniques and the different emplacement schemes for the LLT instrument housing for radiation protection are suggested. A structural concept of an early lunar based telescope is also presented.

Chua, Koon M.↗
DOE OSTI2013

Structural Stability of Human Fibroblast Growth Factor-1 Is Essential for Protective Effects Against Radiation-Induced Intestinal Damage

Purpose: Human fibroblast growth factor-1 (FGF1) has radioprotective effects on the intestine, although its structural instability limits its potential for practical use. Several stable FGF1 mutants were created increasing stability in the order, wild-type FGF1, single mutants (Q40P, S47I, and H93G), Q40P/S47I, and Q40P/S47I/H93G. This study evaluated the contribution of the structural stability of FGF1 to its radioprotective effect. Methods and Materials: Each FGF1 mutant was administered intraperitoneally to BALB/c mice in the absence of heparin 24 h before or after total body irradiation (TBI) with {gamma}-rays at 8-12 Gy. Several radioprotective effects were examined in the jejunum. Results: Q40P/S47I/H93G could activate all subtypes of FGF receptors in vitro much more strongly than the wild-type without endogenous or exogenous heparin. Preirradiation treatment with Q40P/S47I/H93G significantly increased crypt survival more than wild-type FGF1 after TBI at 10 or 12 Gy, and postirradiation treatment with Q40P/S47I/H93G was effective in promoting crypt survival after TBI at 10, 11, or 12 Gy. In addition, crypt cell proliferation, crypt depth, and epithelial differentiation were significantly promoted by postirradiation treatment with Q40P/S47I/H93G. The level of stability of FGF1 mutants correlated with their mitogenic activities in vitro in the absence of heparin; however, preirradiation treatment with the mutants increased the crypt number to almost the same level as Q40P/S47I/H93G. When given 24 h after TBI at 10 Gy, all FGF1 mutants increased crypt survival more than wild-type FGF1, and Q40P/S47I/H93G had the strongest mitogenic effects in intestinal epithelial cells after radiation damage. Moreover, Q40P/S47I/H93G prolonged mouse survival after TBI because of the repair of intestinal damage. Conclusion: These findings suggest that the structural stability of FGF1 can contribute to the enhancement of protective effects against radiation-induced intestinal damage. Therefore, Q40P/S47I/H93G is pharmacologically one of the most promising candidates for clinical applications for radiation-induced gastrointestinal syndrome.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2014

Shielding design for a chip irradiation test facility at SNS - Paper 119

As digital and analog circuits are more and more sophisticatedly integrated, they become increasingly susceptible to single event upsets (SEU), a cause of electronic equipment malfunction induced by cosmic rays with particular hazard potential for aviation equipment. Electronic chips sensitive to SEU have to be tested in a simulated comic ray environment to ensure their reliability. It is found that the spallation induced fast neutron spectrum is very close to the neutron spectrum of the cosmic ray. Hence, a conceptual design study of a chip irradiation test facility is funded by FAA to be carried out at SNS, the world's most powerful accelerator driven facility for neutron scattering studies on materials. Compared to existing/being construct chip irradiation test facilities at LANL and ISIS, SNS can provide wider neutron energy range and much higher fluxes. This study focuses on the aspect of shielding design for such a chip irradiation facility. A number of medium-weighted and heavy materials were examined for efficiency in reducing radiation dose rate. In general, the smaller the target monolith is while satisfying the personnel-protection-driven radiation dose rate limit at its outside, the closer to the target chips could be placed and thus less beam power it demands to satisfy a given irradiation flux requirement. Before proceed to the shielding design, the neutron source coming off the target has to be determined for selecting a best spot for chip irradiation test, in which the incoming fast neutron spectrum approximate most to the atmospheric radiation condition. It also provides a source term for the following shielding design of the irradiation enclosure. (authors)

36 MATERIALS SCIENCE↗
DOE OSTI2017

Neutron-Gamma flux and Dose calculations in a Pressurized Water Reactor (PWR)

The Institute of Radiological Protection and Nuclear Safety (IRSN) acts as technical support to the French nuclear safety authorities. In this context, one of its missions is to improve nuclear safety through the enhancement of knowledge regarding operating nuclear power reactors. The issues concerning the aging and the characterisation of the reactor vessel require knowledge of the neutron and gamma radiation environment on the vessel and beyond. Since few years, ENEA (Energia Nucleare e Energie Alternative, i.e. Nuclear Energy and Alternative Energy agency) and IRSN collaborate on Monte-Carlo simulations and Variance Reduction Techniques (VRT), which are used to determine neutron and gamma spectra in and out of the core. Additionally, IRSN participates in the DISCOMS project, which stands for 'Distributed Sensing for Corium Monitoring and Safety', aiming at examining the status of the third barrier of confinement, in order to define possible mitigation strategies in case of a severe accident, namely: i) reactor pressure vessel breakthrough and corium relocation outside the vessel, ii) reactor pit concrete erosion and iii) corium cooling. One of the IRSN tasks in the frame of the DISCOMS project is to provide the radiation level in terms of neutron and gamma doses and flux energy spectra at various locations. This paper summarizes the study performed on the radiation transport in the Tihange-I Belgian nuclear reactor and contributes to several issues requiring the knowledge of the radiation environment in and outside the reactor vessel. This paper gives an overview of the work presented at the ICRS-13 and RPSD-2016 conference (for more details see the proceedings paper)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2015

MO-AB-201-00: Radiation Safety Officer Update

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2015

MO-AB-201-02: The RSO and The RSC: Challenges and Opportunities

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.

60 APPLIED LIFE SCIENCES↗