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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 991 records · Page 55
All sourcesNASA NTRSDOE OSTI
DOE OSTI2026

Logistics for the 2026 International Nuclear Accident Dosimetry Intercomparison Exercise

The purpose of this exercise is to test participants’ nuclear accident dosimeters (NADs) and personnel to the requirements established by American National Standards Institute (ANSI), Health Physics Society (HPS) standard ANSI/HPS-N13.3-2013 (R2025) Dosimetry for Criticality Accidents. IER-634 is the second nuclear accident dosimetry exercise taking place at the Armed Forces Radiobiology Research Institute (AFRRI) in Bethesda, MD, a Department of Defense (DOD) facility. This effort continues use of the high-dose neutron exposure test bed maintained by the DOD and represents the continued collaboration between the DOD and Department of Energy (DOE). Previous work at AFRRI included a reactor characterization (IER 484) in 2023 and a nuclear accident intercomparison exercise (IER-602) in 2024.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2016

Probabilistic Risk Assessment of Spent Fuel Pool Cooling System Failure Considering Safety and Security Initiating Events

In order to quantify the probable risk associated with a safety system, nuclear safety risk evaluation process is applied which is generally performed in three steps. The first step is to calculate the damage frequency of a critical system. This step is followed by the radioactive source term estimation due to the potential system damage. The final step is the assessment of off-site consequences. The safety risk formula is shown by Eq. (1). P{sub F} is the probability of safety system failure (the probability used describes a random, independent event), and C is the consequence value. R{sub SAF} = P{sub F} * C (1) The security risk associated with an attack on critical infrastructure and/or special nuclear materials theft is usually evaluated using three- term risk equation (probability of attack, probability of adversary success, and consequence). A security threat and the related initiating events are not considered in a pure safety risk analysis. The vulnerability of the physical protection system is performed independently even though the consequence resulting from a security initiating event can be similar to a safety related initiating event and thus gets double counted. The security risk can be calculated using Eq. (2) R{sub SEC} = P{sub A} * P{sub S} * C (2) PA is the probability of attack, P{sub S} is the probability of adversary success (P{sub S} = 1 - P{sub I} P{sub N}). P{sub I} being the probability of interruption which accounts for the probabilities of detection of all timely detection elements along an adversary path. PN being the probability of neutralization: the result of engagement of the response force with the adversaries after the interruption has occurred. C is the consequence magnitude from a successful attack. The two security probabilities do not describe random, independent events. As a result, because of the differences in the randomness and independence of the respective safety and security probabilities, the safety and the security risks are currently calculated separately. The consequence term in nuclear safety and security risk evaluation have the same definition. An effort is made here to study the effect on the overall risk by considering security initiating events along with the subsequent failure of the intermediate safety element. The target selected is a spent fuel storage pool for analyzing the public risk arising from the interplay between nuclear security and safety initiating events. EASI (Estimate of Adversary Sequence Interruption) model is used to calculate the probability of interruption related to a security system that leads to the calculation of the security initiating event frequency. Further progression of this initiating security event to a top event is analyzed using a Probabilistic Safety Assessment (PSA) tool, SAPHIRE (version 8) to obtain a joint pool damage frequency. For the progression of events leading to a top event, the failure of the intermediate safety elements is assumed to be external random events such as heavy load drop and fire events. The objectives of this study is to (1) determine the double accounting of frequency of failure, risk and allocated resources in the scenario of a non-random security initiating event leading to a safety random event chain (2) compare the damage frequency from pure security with the frequency of combined security-safety failure event and pure safety failure events. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2014

Repeated Nrf2 stimulation using sulforaphane protects fibroblasts from ionizing radiation

Most of the cytotoxicity induced by ionizing radiation is mediated by radical-induced DNA double-strand breaks. Cellular protection from free radicals can be stimulated several fold by sulforaphane-mediated activation of the transcription factor Nrf2 that regulates more than 50 genes involved in the detoxification of reactive substances and radicals. Here, we report that repeated sulforaphane treatment increases radioresistance in primary human skin fibroblasts. Cells were either treated with sulforaphane for four hours once or with four-hour treatments repeatedly for three consecutive days prior to radiation exposure. Fibroblasts exposed to repeated-sulforaphane treatment showed a more pronounced dose-dependent induction of Nrf2-regulated mRNA and reduced amount of radiation-induced free radicals compared with cells treated once with sulforaphane. In addition, radiation- induced DNA double-strand breaks measured by gamma-H2AX foci were attenuated following repeated sulforaphane treatment. As a result, cellular protection from ionizing radiation measured by the 5-ethynyl-2′-deoxyuridine (EdU) assay was increased, specifically in cells exposed to repeated sulforaphane treatment. Sulforaphane treatment was unable to protect Nrf2 knockout mouse embryonic fibroblasts, indicating that the sulforaphane-induced radioprotection was Nrf2-dependent. Moreover, radioprotection by repeated sulforaphane treatment was dose-dependent with an optimal effect at 10 uM, whereas both lower and higher concentrations resulted in lower levels of radioprotection. Our data indicate that the Nrf2 system can be trained to provide further protection from radical damage. - Highlights: • Repeated treatment with sulforaphane protects fibroblasts from ionizing radiation • Repeated sulforaphane treatment attenuates radiation induced ROS and DNA damage • Sulforaphane mediated protection is Nrf2 dependent.

60 APPLIED LIFE SCIENCES↗
NASA NTRS2011

Review of Nuclear Physics Experiments for Space Radiation

Human space flight requires protecting astronauts from the harmful effects of space radiation. The availability of measured nuclear cross section data needed for these studies is reviewed in the present paper. The energy range of interest for radiation protection is approximately 100 MeV/n to 10 GeV/n. The majority of data are for projectile fragmentation partial and total cross sections, including both charge changing and isotopic cross sections. The cross section data are organized into categories which include charge changing, elemental, isotopic for total, single and double differential with respect to momentum, energy and angle. Gaps in the data relevant to space radiation protection are discussed and recommendations for future experiments are made.

Norbury, John W.↗
DOE OSTI2014

Design of Photosensitive Glass based X-ray Anti-scattering Grid by using MCNP code - Paper 6

It is required to protect individual against the dangers of ionizing radiation from medical exposure. And in order to increase accuracy of radiography and radiotherapy, it is essential to remove scattered radiation. Therefore, to satisfy these, proper anti-scattering x-ray grid is required. An anti-scattering grid is composed of penetration material and shielding material. Many studies have been carried out about fabricating x-ray anti-scattering grid by lithography. Lithography gives benefit of getting high aspect ratio and makes it easy to have smooth and thin fabrication. Photosensitive glass is focused on because it has advantages for laser fabrication. UV laser micro fabrication technology is used widely in VLSI, and other micro systems. These technologies can be employed into anti-scattering grid because it is also requires precise fabrication. In this study, it includes computer simulation of grid with photosensitive glass. Some models are adopted and analyzed by using MCNP code and the efficiencies are estimated. (authors)

36 MATERIALS SCIENCE↗
DOE OSTI2025

Fission gas trapped in Chornobyl fuel microparticles reveals details of reactor operations

The isotopic ratios of fission gas would provide important source information of a nuclear fuel sample found in the environment. However, it is believed that during a reactor accident like Chornobyl all fission gas is lost and that the radioactive particles found in the Chornobyl Exclusion Zone today are depleted in gases by the initial explosion and subsequent fire. We disprove this hypothesis by detection and analysis of trapped krypton and xenon in these particles. Our analysis of krypton and xenon isotopes by noble gas mass spectroscopy in combination with resonance ionization mass spectrometry establishes that important information about reactor operations like age, neutron flux and plutonium fission fraction can still be reconstructed from individual micrometer-sized particles even after decades of weathering in the environment.

Chornobyl↗
NASA NTRS1992

Radiation shielding estimates for manned Mars space flight

In the analysis of the required radiation shielding protection of spacecraft during a Mars flight, specific effects of solar activity (SA) on the intensity of galactic and solar cosmic rays were taken into consideration. Three spaceflight periods were considered: (1) maximum SA; (2) minimum SA; and (3) intermediate SA, when intensities of both galactic and solar cosmic rays are moderately high. Scenarios of spaceflights utilizing liquid-propellant rocket engines, low- and intermediate-thrust nuclear electrojet engines, and nuclear rocket engines, all of which have been designed in the Soviet Union, are reviewed. Calculations were performed on the basis of a set of standards for radiation protection approved by the U.S.S.R. State Committee for Standards. It was found that the lowest estimated mass of a Mars spacecraft, including the radiation shielding mass, obtained using a combination of a liquid propellant engine with low and intermediate thrust nuclear electrojet engines, would be 500-550 metric tons.

Non-NASA Center↗
DOE OSTI2020

Estimating a protection factor from homemade facemasks for Los Alamos radioactive aerosols

The Los Alamos National Laboratory has required usage of facemasks “whenever interacting with or near others." The present document estimates the respiratory protection factor of homemade facemasks to be 1.4 and 1.2 for aerosol particles, below and above 0.3 μm diameter, respectively. This includes an estimated leakage of 70% and 52% for aerosol particles below and above 0.3 μm diameter, respectively.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2017

A Rapid Method for Quantification OF 242Pu in Urine Using Extraction Chromatography and ICP-MS

Occupational exposure to plutonium is generally monitored through analysis of urine samples. Typically, plutonium is separated from the sample and other actinides, and the concentration is determined using alpha spectroscopy. Current methods for separations and analysis are lengthy and require long count times. A new method for monitoring occupational exposure levels of plutonium has been developed, which requires fewer steps and overall less time than the alpha spectroscopy method. In this method, the urine is acidified, and a 239 Pu internal standard is added. The urine is digested in a microwave oven, and plutonium is separated using an Eichrom TRU Resin column. The plutonium is eluted, and the eluant is injected directly into the Inductively Coupled Plasma–Mass Spectrometer (ICP-MS). Compared to a direct “dilute and shoot” method, a 30-fold improvement in sensitivity is achieved. This method was validated by analyzing several batches of spiked samples. Based on these analyses, a combined standard uncertainty plot, which relates uncertainty to concentration, was produced. As a result, the MDA 95 was calculated to be 7.0 × 10 –7 μg L –1 , and the Lc95 was calculated to be 3.5 × 10 –7 μg L –1 for this method.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2014

Estimated External Doses to Members of the Public from Patients with {sup 131}I Treatment - Paper 143

To protect individuals from the radiation emitted by a patient receiving {sup 131}I treatment a licensee must estimate the maximum likely effective dose to members of the public. Under current guidance by the United States Nuclear Regulatory Commission (NRC), a licensee may authorize the release of the patient if the effective dose is unlikely to exceed 5 mSv. NRC provides guidance to its licensees, in NRC Regulatory Guide 8.39, on acceptable methods that may be used to calculate the dose to a member of the public that may result from releasing the patient. To further assist licensees in implementing the regulation, NRC used conservative assumptions to estimate the activity of radionuclide in a patient, and the dose rate at 1 meter from the patient, that would be indicators of a potential dose to a member of the public of 5 mSv. Licensees may use these tables as operational criteria for releasing a patient if the conservative assumptions are considered acceptable. Licensees may also perform their own calculations, using case-specific assumptions, to show compliance with 5 mSv release criterion. The scope of this work is to provide dose coefficients for a variety of plausible public exposure scenarios that could be used by licensees to to show compliance. In the patient-specific calculations, the licensee is free to consider factors such as occupancy factor, effective half-life of the radionuclide in the patient's body, and tissue shielding. A conservative method of calculating the maximum likely dose to members of the public is provided in NRC Reg. Guide 8.39, which assumes no tissue attenuation of by the patient's body, no biological component that reduces the effective half-life of the radionuclide, and the patient's body burden is a point source. The assumption of no biological removal from the body introduces some conservatism into dose estimates for {sup 131}I. Also, it has been shown that the assumption of a point source with no tissue attenuation substantially overestimates the dose rate to nearby persons. The current method for calculating the maximum dose rate to members of the public from a nuclear medicine patient provided in US-NRC Regulatory Guide 8.39 assumes the patient's body burden is a point-source. Lack of consideration of tissue attenuation by the patient's body and biological removal of the radionuclide leads to a substantial overestimate of the actual external dose rate to a nearby member of the public. However, use of these assumptions in estimating potential dose to a member of the public simplifies the calculations considerably and, although generally conservative, the calculations serve as a useful screening tool. Many, if not most patients, could be released on that basis. If not, then refined calculations may be used, and the coefficients described in this paper provide one of the means for refining the calculations in cases where the screening calculations were not adequate. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2015

Response of the REWARD detection system to the presence of a Radiological Dispersal Device

In recent years an increased international concern has emerged about the radiological and nuclear (RN) threats associated with the illicit trafficking of nuclear and radioactive materials that could be potentially used for terrorist attacks. The objective of the REWARD (Real Time Wide Area Radiation Surveillance System) project, co-funded by the European Union 7. Framework Programme Security, consisted in building a mobile system for real time, wide area radiation surveillance, using a CdZnTe detector for gamma radiation and a neutron detector based on novel silicon technologies. The sensing unit includes a GPS system and a wireless communication interface to send the data remotely to a monitoring base station, where it will be analyzed in real time and correlated with historical data from the tag location, in order to generate an alarm when an abnormal situation is detected. Due to its portability and accuracy, the system will be extremely useful in many different scenarios such as nuclear terrorism, lost radioactive sources, radioactive contamination or nuclear accidents. This paper shortly introduces the REWARD detection system, depicts some terrorist threat scenarios involving radioactive sources and special nuclear materials and summarizes the simulation work undertaken during the past three years in the framework of the REWARD project. The main objective consisted in making predictions regarding the behavior of the REWARD system in the presence of a Radiological Dispersion Device (RDD), one of the reference scenarios foreseen for REWARD, using the Monte Carlo simulation program MCNP6. The reference scenario is characterized in detail, from the i) radiological protection, ii) radiation detection requirements and iii) communications points of view. Experimental tests were performed at the Fire Brigades Facilities in Rome and at the Naples Fire Brigades, and the results, which validate the simulation work, are presented and analyzed. The response of the REWARD detection system to the presence of an RDD is predicted and discussed. (authors)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2017

Plasma Retention and Systemic Kinetics of 90 Sr Intramuscularly Injected in Female Nonhuman Primates

Thirteen female Rhesus macaques were intramuscularly injected with 90 Sr(NO 3 ) 2 diluted in sodium citrate solution. The biokinetic data from these animals were compared against the predictions of the NCRP 156 wound models combined with the ICRP systemic models. We observed observed that the activities measured in plasma of these nonhuman primates (NHPs) were consistently lower than those predicted by the default human biokinetic models. The urinary excretion from the NHPs at times immediately after injection was much greater than that in humans. The fecal excretion rates were found to be in relatively better agreement with humans. Similarly, the activities retained in the skeleton of the NHPs were lower than that in humans. These differences were attributed to the higher calcium diet of the NHPs (0.03 to 0.12 g/d/kg body weight) compared to that of humans. These observations were consistent with the early animal and human studies that showed the effect of calcium on strontium metabolism, specifically urinary excretion. Strontium is preferentially filtered at a much higher rate in kidneys than calcium because it is less completely bound to protein than is calcium. Furthermore, these differences, along with large inter-animal variability, should be considered when estimating the behavior of Sr in humans from the metabolic data in animals or vice-versa.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2015

SU-E-T-801: Verification of Dose Information Passed Through 3D-Printed Products

Purpose: When quality assurance (QA) of patient treatment beam is performed, homogeneous water equivalent phantom which has different structure from patient’s internal structure is normally used. In these days, it is possible to make structures which have same shapes of human organs with commercialization of 3D-printer. As a Result, structures with same shape of human organs made by 3D-printer could be used to test qualification of treatment beam with greater accuracy than homogeneous water phantom. In this study, we estimated the dose response of 3D-printer materials to test the probability as a humanoid phantom or new generation of compensator tool. Methods: The rectangular products with variety densities (50%, 75% and 100%) were made to verify their characteristics. The products for experiment group and solid water phantom and air for control group with 125 cubic centimeters were put on solid water phantom with enough thickness. CT image of two products were acquired to know their HU values and to know about their radiologic characteristics. 6MV beams with 500MU were exposed for each experiment. Doses were measured behind the 3D-printed products. These measured doses were compared to the results taken by TPS. Results: Absorbed dose penetrated from empty air is normalized to 100%. Doses measured from 6MV photon beams penetrated from 50%, 75% and 100% products were 99%, 96% and 84%, respectively. HU values of 50%, 75% and 100% products are about −910, −860 and −10. Conclusion: 3D-printer can produce structures which have similar characteristics with human organ. These results would be used to make similar phantoms with patient information. This work was supported by the Nuclear Safety Research Program (Grant No. 1305033 and 1403019) of the Korea Radiation Safety Foundation and the Nuclear Safety and Security Commission and Radiation Technology Development Program (2013M2A2A4027117) of the Republic of Korea.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2016

SU-B-BRA-09: 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 OSTI2016

SU-B-BRA-00: The Medical Physicist Value Proposition for Tomorrow and Today

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 OSTI2017

Nuclear Photonics

A review of works performed at the Institute for Nuclear Research of the Russian Academy of Sciences and at the International Laser Center of the Moscow State University in the context of the new research area called “nuclear photonics” is presented. Nuclear photonics is based on creation of the new-generation gamma-ray sources which make it possible to solve a number of fundamental and applied problems, including research of low-energy photonuclear reactions, namely, investigation of collective excitations of nuclei near the threshold (pygmy resonances); nuclear safety assurance; production of low-energy positron beams; and phase-contrast X-ray imaging.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2017

Second-order Kinetics of DTPA and Plutonium in Rat Plasma

We report that in 2008, Serandour et al. reported on their in vitro experiment involving rat plasma samples obtained after an intravenous intake of plutonium citrate. Different amounts of DTPA were added to the plasma samples and the percentage of low-molecular-weight plutonium measured. Only when the DTPA dosage was three orders of magnitude greater than the recommended 30 μmol/kg was 100% of the plutonium apparently in the form of chelate. These data were modeled assuming three competing chemical reactions with other molecules that bind with plutonium. Here, time-dependent second-order kinetics of these reactions are calculated, intended eventually to become part of a complete biokinetic model of DTPA action on actinides in laboratory animals or humans. The probability distribution of the ratio of stability constants for the reactants was calculated using Markov Chain Monte Carlo. In conclusion, these calculations substantiate that the inclusion of more reactions is needed in order to be in agreement with known stability constants.

61 RADIATION PROTECTION AND DOSIMETRY↗