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All sourcesNASA NTRSDOE OSTI
DOE OSTI2015

WE-AB-213-00: Developments in International Medical Physics Collaborations in Africa and Latin America

The African Affairs Subcommittee (AA-SC) of the AAPM will present a multi-institutional approach to medical physics support in Africa. Current work to increase the quality of care and level of safety for the medical physics practice in Senegal, Ghana, and Zimbabwe will be presented, along with preliminary projects in Nigeria and Botswana. Because the task of addressing the needs of medical physics in countries across Africa is larger than one entity can accomplish on its own, the AA-SC has taken the approach of joining forces with multiple organizations such as Radiating Hope and TreatSafely (NGO’s), the IAEA, companies like BrainLab, Varian and Elekta, medical volunteers and academic institutions such as NYU and Washington University. Elements of current projects include: 1) Distance training and evaluation of the quality of contouring and treatment planning, teaching treatment planning and other subjects, and troubleshooting using modern telecommunications technology in Senegal, Ghana, and Zimbabwe; 2) Assistance in the transition from 2D to 3D in Senegal and Zimbabwe; 3) Assistance in the transition from 3D to IMRT using in-house compensators in Senegal; 4) Modernizing the cancer center in Senegal and increasing safety and; 5) Training on on 3D techniques in Ghana; 6) Assisting a teaching and training radiation oncology center to be built in Zimbabwe; 7) Working with the ISEP Program in Sub-Saharan Africa; 8) Creating instructional videos on linac commissioning; 9) Working on a possible collaboration to train physicists in Nigeria. Building on past achievements, the subcommittee seeks to make a larger impact on the continent, as the number and size of projects increases and more human resources become available. The State of Medical Physics Collaborations and Projects in Latin America Sandra Guzman (Peru) The lack of Medical Physicists (MP) in many Latin American (LA) countries leads to recruitment of professionals with incomplete education. In most LA countries only one MP responsible for each Center is currently mandated. Currently there is a large disparity among MP training programs and there is significant debate about the standards of MP graduate education in many LA countries. There are no commonly recognized academic programs, not enough clinical training sites and clinical training is not typically considered as part of the MP work. Economic pressures and high workloads also impede the creation of more training centers. The increasing need of qualified MPs require establishing a coordinated system of national Education & Training Centers (ETC), to meet the international standards of education and training in Medical Physics. This shortfall calls for support of organizations such as the IOMP, AAPM, ALFIM, IAEA, etc. Examples from various LA countries, as well as some proposed solutions, will be presented. In particular, we will discuss the resources that the AAPM and its members can offer to support regional programs. The ‘Medical Imaging’ physicist in the emerging world: Challenges and opportunities - Caridad Borrás (WGNIMP Chair) While the role of radiation therapy physicists in the emerging world is reasonably well established, the role of medical imaging physicists is not. The only perceived needs in radiology departments are equipment quality control and radiation protection, tasks that can be done by a technologist or a service engineer. To change the situation, the International Basic Safety Standard, which is adopted/adapted world-wide as national radiation protection regulations, states: “For diagnostic radiological procedures and image guided interventional procedures, the requirements of these Standards for medical imaging, calibration, dosimetry and quality assurance, including the acceptance and commissioning of medical radiological equipment, are fulfilled by or under the oversight of, or with the documented advice of a medical physicist, whose degree of involvement is determined by the complexity of the radiological procedures and the associated radiation risks”. Details on how these requirements can be carried out in resource-limited settings will be described. IAEA support to medical physics in Africa and Latin America: achievements and challenges Ahmed Meghzifene (IAEA) Shortage of clinically qualified medical physicists in radiotherapy and imaging, insufficient and inadequate education and training programs, as well as a lack of professional recognition were identified as the main issues to be addressed by the IAEA. The IAEA developed a series of integrated projects aiming specifically at promoting the essential role of medical physicists in health care, developing harmonized guidelines on dosimetry and quality assurance, and supporting education and clinical training programs. The unique feature of the IAEA approach is support it provides for implementation of guidelines and education programs in Member States through its technical cooperation project. The presentation will summarize IAEA support to Latin America and Africa in the field of medical physics and will highlight how the new International Basic Safety Standards are expected to impact the medical physics practice in low and middle income countries. Learning Objectives: Learn about the shortage of qualified Medical Physicists in Africa and Latin America. Understand the reasons of this shortage. Learn about the ways to improve the situation and AAPM role in this process.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2018

Nevada National Security Site Radiological Control Manual

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO). (Activities conducted under the purview of the U.S. Department of Energy, Office of Environmental Management Nevada[(EM Nevada] may require additional approval authorities as described in the EM Nevada Prime Contractor’s implementation plan.) Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, “Occupational Radiation Protection.” This manual represents policies, guidelines, and best practices for implementing the DOE/NV/03624--0082, “Nevada National Security Site Radiation Protection Program,” (NNSS RPP) according to the requirements of 10 CFR 835.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2016

Annular Core Research Reactor High Bay Neutron Energy Spectrum Measurements

The Annular Core Research Reactor (ACRR) recently underwent a multi-department effort to characterize the neutron energy leakage spectra in the reactor High Bay for multiple shielding configurations. The ACRR Operations Department identified and obtained a Rotating Neutron Spectrometer (ROSPEC) from Los Alamos National Laboratories (LANL) for obtaining neutron energy spectra. Spectra were obtained in the following facility configurations; Fuel Ringed External Cavity, Version II (FREC-II) decoupled with the standard FREC shield plug installed with the following operational permutations: the 4-inch central cavity (CC) shield plug removed in both a free-field (FF) and 44(3y (Blead-boron (LB-44) bucket neutron modifier configuration, fully shielded CC plug FF condition, neutron radiography collimator aperture settings 250:1, 125:1, and 65:1, FREC-II coupled with both the lightweight (2T1) and standard shield plug configurations. The ROSPEC spectrum results were unfolded, evaluated and weighted using the International Commission on Radiation Protection (ICRP) 103 neutron radiation weighting factors to obtain a ratio amongst the different shielding configurations at the ACRR. Results of the collected spectra confirm that the predominant neutron energy range in the High Bay area is less than or equal to 250 keV.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2021

RCT: 2.01 Radiological Documentation [Slides]

10 CFR 835 establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of DOE activities. It is important to maintain the proper documentation to ensure that these standards and requirements are being met. An RCT plays a vital role in supporting these requirements through proper documentation.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2023

RCT Continuing Training: Unit 1 Exam Review [Slides]

Terminal Objective: Given the need to perform duties as an RCT, recognize fundamental concepts of radiation protection, in accordance with DOE-HDBK-1122, Radiation Control Technician Training.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2024

RCT Module: 2.01 Radiological Documentation [Slides]

10 CFR 835 establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of DOE activities. It is important to maintain the proper documentation to ensure that these standards and requirements are being met. An RCT plays a vital role in supporting these requirements through proper documentation.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2017

Enhanced Monte Carlo Simulation of the Voxel Phantom Lattice Submersed in a Contaminated Air Environment

External dose coefficient calculations reported for submersions in semi-infinite clouds, as in the Environmental Protection Agency: Federal Guidance Report 12, assume a person standing on the ground submerged in a radioactive cloud. In the scope of the work presented here, Oak Ridge National Laboratory's Center for Radiation Protection Knowledge has computed dose coefficients for monoenergetic photons, electrons, and positrons for worker exposures in three rooms of finite sizes representing an office, laboratory, and warehouse. In the process of simulating these exposures, International Commission on Radiological Protection (ICRP) Publication 110 reference adult male and female voxel phantom lattices were placed in the rooms filled with contaminated air. It was apparent that additional simulations were need to treat the non-tissue voxels surrounding the phantoms as containing the contaminated air. Dose coefficients for three room sizes representing an office, laboratory, and warehouse were computed. The coefficients for electrons exhibit little dependence on room size for most energies. However, for organs within the range of electron transport, the dose from source activity within the non-tissue voxels of the lattice surrounding the phantom becomes increasingly important. The photon dose coefficients vary based on room size because of longer mean free paths. It is important to include the air surrounding the voxel phantom within the voxel lattice in the calculations, when simulating a voxel phantom submersed in air for source particle energies below 200-300 keV, otherwise, the organ dose coefficient would be underestimated. Organ and effective dose coefficients for each gender, energy, and room size will be tabulated on the Oak Ridge National Laboratory - Center for Radiation Protection Knowledge website: http://ornl.gov/crpk.

61 RADIATION PROTECTION AND DOSIMETRY↗
NASA NTRS2008

Spacecraft Radiator Freeze Protection Using a Regenerative Heat Exchanger with Bypass Setpoint Temperature Control

Spacecraft radiators are sized for their maximum heat load in their warmest thermal environment, but must operate at reduced heat loads and in colder environments. For systems where the radiator environment can be colder than the working fluid freezing temperature, radiator freezing becomes an issue. Radiator freezing has not been a major issue for the Space Shuttle and the International Space Station (ISS) active thermal control systems (ATCSs) because they operate in environments that are warm relative to the freezing point of their external coolants (Freon-21 and ammonia, respectively). For a vehicle that lands at the Lunar South Pole, the design thermal environment is 215K, but the radiator working fluid must also be kept from freezing during the 0 K sink of transit. A radiator bypass flow control design such as those used on the Space Shuttle and ISS requires more than 30% of the design heat load to avoid radiator freezing during transit - even with a very low freezing point working fluid. By changing the traditional ATCS architecture to include a regenerating heat exchanger inboard of the radiator and by using a regenerator bypass flow control valve to maintain system setpoint, the required minimum heat load can be reduced by more than half. This gives the spacecraft much more flexibility in design and operation. The present work describes the regenerator bypass ATCS setpoint control methodology. It includes analytical results comparing the performance of this system to the traditional radiator bypass system. Finally, a summary of the advantages of the regenerator bypass system are presented.

Ungar, Eugene K.↗
NASA NTRS2001

Measurement of Charged Particle Interactions in Spacecraft and Planetary Habitat Shielding Materials

The Microgravity Materials Program, through its 98-HEDS-04 Research Announcement, has called for research to support 'enhanced human radiation protection through the development of light weight soft goods with high radiation protection characteristics.' Given the nature of the particle flux from the Galactic Cosmic Radiation (GCR), and the many constraints on the depth and type of shielding in spacecraft and planetary habitats, it is clear that the health risks these particles present to astronauts in deep space cannot be entirely eliminated. It is the objective of this project to develop a highly accurate model of GCR transport so that NASA can develop and validate the properties of protective shielding materials with the best available information. The validity of the GCR transport model depends in large part on having accurate and precise input data in the form of the charge-changing and fragment production cross sections for the heavy ions of greatest biological significance. The accuracy of the transport model can be evaluated and enhanced by employing the following a three-step strategy: (1) New cross section data will be made available to the NASA-Langley scientists responsible for the transport codes, and will be used as inputs to the codes; (2) The codes will be used to predict additional cross sections and/or details of the radiation field behind realistic shielding arrangements, where the materials and configurations may be quite complex. Mock-ups of the shielding configurations suitable for use in accelerator experiments will obtained by the NASA-Langley co-investigators; and (3) The transport model predictions will be tested in accelerator-based experiments. The time scale for one pass through these steps is well-suited to a four-year schedule. Over a longer term, these steps may be repeated, leading to still further refinements of the transport code, new predictions, and an additional round of measurements, until the desired predictive accuracy is achieved. The focus of this work is primarily on the first of these steps, the determination of fragmentation cross sections, which will be the main task in years one and two. The detailed strategy for carrying out the remainder of the program is more difficult to specify, as it depends on unpredictable factors such as the extent to which the transport model must be modified, schedules for accelerator time, target fabrication, etc.

Zeitlin, C.↗
DOE OSTI2021

LANL Environmental ALARA Program Status Report for CY 2020

Los Alamos National Laboratory (LANL) ensures that radiation exposures to members of the public and the environment from LANL operations, past and present, are below regulatory thresholds and are as low as reasonably achievable (ALARA) through compliance with Department of Energy (DOE) Order 458.1 Radiation Protection for the Public and the Environment (DOE 2020), and LANL Functional Series Documents EPC-ES-FSD-004,Environmental Radiation Protection, (LANL 2020a) and EPC-ES-FSD-003, Los Alamos National Laboratory Environmental ALARA Program (LANL 2020b). These documents provide related program authorities, responsibilities, descriptions, processes, and thresholds for conducting qualitative and quantitative ALARA analyses for prospective and actual radiation exposures to the public and to the environment resulting from DOE activities conducted on the LANL site.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2015

The development of remote wireless radiation dose monitoring system

Internet of things (IoT) technology has recently shown a large flow of IT trends in human life. In particular, our lives are now becoming integrated with a lot of items around the 'smart-phone' with IoT, including Bluetooth, Near Field Communication (NFC), Beacons, WiFi, and Global Positioning System (GPS). Our project focuses on the interconnection of radiation dosimetry and IoT technology. The radiation workers at a nuclear facility should hold personal dosimeters such as a Thermo-Luminescence Dosimeter (TLD), an Optically Stimulated Luminescence Dosimeter (OSL), pocket ionization chamber dosimeters, an Electronic Personal Dosimeter (EPD), or an alarm dosimeter on their body. Some of them have functions that generate audible or visible alarms to radiation workers in a real working area. However, such devices used in radiation fields these days have no functions for communicating with other areas or the responsible personnel in real time. In particular, when conducting a particular task in a high dose area, or a number of repair works within a radiation field, radiation dose monitoring is important for the health of the workers and the work efficiency. Our project aims at the development of a remote wireless radiation dose monitoring system (RWRD) that can be used to monitor the radiation dose in a nuclear facility for radiation workers and a radiation protection program In this project, a radiation dosimeter is the detection device for personal radiation dose, a smart phone is the mobile wireless communication tool, and, Beacon is the wireless starter for the detection, communication, and position of the worker using BLE (Bluetooth Low Energy). In this report, we report the design of the RWRD and a demonstration case in a real radiation field. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2014

A GSK-3β Inhibitor Protects Against Radiation Necrosis in Mouse Brain

Purpose: To quantify the effectiveness of SB415286, a specific inhibitor of GSK-3β, as a neuroprotectant against radiation-induced central nervous system (brain) necrosis in a mouse model. Methods and Materials: Cohorts of mice were treated with SB415286 or dimethyl sulfoxide (DMSO) prior to irradiation with a single 45-Gy fraction targeted to the left hemisphere (brain) using a gamma knife machine. The onset and progression of radiation necrosis (RN) were monitored longitudinally by noninvasive in vivo small-animal magnetic resonance imaging (MRI) beginning 13 weeks postirradiation. MRI-derived necrotic volumes for SB415286- and DMSO-treated mice were compared. MRI results were supported by correlative histology. Results: Mice treated with SB415286 showed significant protection from radiation-induced necrosis, as determined by in vivo MRI with histologic validation. MRI-derived necrotic volumes were significantly smaller at all postirradiation time points in SB415286-treated animals. Although the irradiated hemispheres of the DMSO-treated mice demonstrated many of the classic histologic features of RN, including fibrinoid vascular necrosis, vascular telangiectasia, hemorrhage, and tissue loss, the irradiated hemispheres of the SB415286-treated mice consistently showed only minimal tissue damage. These studies confirmed that treatment with a GSK-3β inhibitor dramatically reduced delayed time-to-onset necrosis in irradiated brain. Conclusions: The unilateral cerebral hemispheric stereotactic radiation surgery mouse model in concert with longitudinal MRI monitoring provided a powerful platform for studying the onset and progression of RN and for developing and testing new neuroprotectants. Effectiveness of SB415286 as a neuroprotectant against necrosis motivates potential clinical trials of it or other GSK-3β inhibitors.

62 RADIOLOGY AND NUCLEAR MEDICINE↗
DOE OSTI2015

TU-CD-303-00: In Memoriam of Warren Sinclair: Physics Applications for New Radiobiology

The Medical Physics and Radiation Protection communities lost one of their true pioneers in May, 2014 with the passing of Warren K. Sinclair, Ph.D. He received his Doctorate in Physics at the University of London, U.K. He was a fellow of the Institute of Physics and a Certified Health Physicist. After a number of posts at Hospitals and Universities in the U.K. and New Zealand, he became the Head, Physics Department at the M.D. Anderson Hospital, Houston, TX. He held a number of academic physics positions with the University of Texas, Austin at the main campus and at the Postgraduate School of Medicine, Houston. He later served as a Senior Biophysicist, Division Director, and then Associate Laboratory Director for Biomedical Division Director, and then Associate Laboratory Director for Biomedical and Environmental Research at the Argonne National Laboratory, IL. He had additional academic appointments at the University of California, Berkeley; Northern Illinois University; the University of Illinois (Chicago Circle Campus); and the University of Chicago. Warren was a charter member of the AAPM and a leader in many communities: President of the AAPM from 1960 to 1961 and the Journal Editor from 1964 to 1969, the 2nd President of the NCRP from 1977 to 1991, and the President of the Radiation Research Society from 1978 to 1979. His many awards included the William D. Coolidge Award in 1986. Even this barely scratches the surface of the many other organizations he served with and influenced including the ICRP, IOP, RSNA, SNM, and UNSCEAR. His research interests resulted in publications from 1948 to the 1990s in many aspects (physical and biological) of radiotherapy and the effects of ionizing radiation in general, leading to early definitions of RBE values for megavoltage radiotherapy as well as contributing to the development of the modern framework for radiation protection worldwide. Warren was not a retiring person and even after moving to NCRP President Emeritus status continued to provide advice and comments on publications and to mentor others until the time of his passing. Sadly, Warren’s long-time wife Joy passed away in December, 2014 but he is survived by his son Bruce and daughter Roslyn, 2 grandchildren and 4 great-grandchildren.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2015

TU-CD-303-01: Memorial to Warren Sinclair - Memorial Lecturer

The Medical Physics and Radiation Protection communities lost one of their true pioneers in May, 2014 with the passing of Warren K. Sinclair, Ph.D. He received his Doctorate in Physics at the University of London, U.K. He was a fellow of the Institute of Physics and a Certified Health Physicist. After a number of posts at Hospitals and Universities in the U.K. and New Zealand, he became the Head, Physics Department at the M.D. Anderson Hospital, Houston, TX. He held a number of academic physics positions with the University of Texas, Austin at the main campus and at the Postgraduate School of Medicine, Houston. He later served as a Senior Biophysicist, Division Director, and then Associate Laboratory Director for Biomedical Division Director, and then Associate Laboratory Director for Biomedical and Environmental Research at the Argonne National Laboratory, IL. He had additional academic appointments at the University of California, Berkeley; Northern Illinois University; the University of Illinois (Chicago Circle Campus); and the University of Chicago. Warren was a charter member of the AAPM and a leader in many communities: President of the AAPM from 1960 to 1961 and the Journal Editor from 1964 to 1969, the 2nd President of the NCRP from 1977 to 1991, and the President of the Radiation Research Society from 1978 to 1979. His many awards included the William D. Coolidge Award in 1986. Even this barely scratches the surface of the many other organizations he served with and influenced including the ICRP, IOP, RSNA, SNM, and UNSCEAR. His research interests resulted in publications from 1948 to the 1990s in many aspects (physical and biological) of radiotherapy and the effects of ionizing radiation in general, leading to early definitions of RBE values for megavoltage radiotherapy as well as contributing to the development of the modern framework for radiation protection worldwide. Warren was not a retiring person and even after moving to NCRP President Emeritus status continued to provide advice and comments on publications and to mentor others until the time of his passing. Sadly, Warren’s long-time wife Joy passed away in December, 2014 but he is survived by his son Bruce and daughter Roslyn, 2 grandchildren and 4 great-grandchildren.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2014

Beam characteristics of energy-matched flattening filter free beams

Purpose: Flattening filter free (FFF) linear accelerators can increase treatment efficiency and plan quality. There are multiple methods of defining a FFF beam. The Elekta control system supports tuning of the delivered FFF beam energy to enable matching of the percentage depth-dose (PDD) of the flattened beam at 10 cm depth. This is compared to FFF beams where the linac control parameters are identical to those for the flattened beam. All beams were delivered on an Elekta Synergy accelerator with an Agility multi-leaf collimator installed and compared to the standard, flattened beam. The aim of this study is to compare “matched” FFF beams to both “unmatched” FFF beams and flattened beams to determine the benefits of matching beams. Methods: For the three modes of operation 6 MV flattened, 6 MV matched FFF, 6 MV unmatched FFF, 10 MV flattened, 10 MV matched FFF, and 10 MV unmatched FFF beam profiles were obtained using a plotting tank and were measured in steps of 0.1 mm in the penumbral region. Beam penumbra was defined as the distance between the 80% and 20% of the normalized dose when the inflection points of the unflattened and flattened profiles were normalized with the central axis dose of the flattened field set as 100%. PDD data was obtained at field sizes ranging from 3 cm × 3 cm to 40 cm × 40 cm. Radiation protection measurements were additionally performed to determine the head leakage and environmental monitoring through the maze and primary barriers. Results: No significant change is made to the beam penumbra for FFF beams with and without PDD matching, the maximum change in penumbra for a 10 cm × 10 cm field was within the experimental error of the study. The changes in the profile shape with increasing field size are most significant for the matched FFF beam, and both FFF beams showed less profile shape variation with increasing depth when compared to flattened beams, due to consistency in beam energy spectra across the radiation field. The PDDs of the FFF beams showed less variation with field size, the d{sub max} value was deeper for the matched FFF beam than the FFF beam and deeper than the flattened beam for field sizes greater than 5 cm × 5 cm. The head leakage when using the machine in FFF mode is less than half that for a flattened beam, but comparable for both FFF modes. The radiation protection dose-rate measurements show an increase of instantaneous dose-rates when operating the machines in FFF mode but that increase is less than the ratio of MU/min produced by the machine. Conclusions: The matching of a FFF beam to a flattened beam at a depth of 10 cm in water by increasing the FFF beam energy does not reduce any of the reported benefits of FFF beams. Conversely, there are a number of potential benefits resulting from matching the FFF beam; the depth of maximum dose is deeper, the out of field dose is potentially reduced, and the beam quality and penetration more closely resembles the flattened beams currently used in clinical practice, making dose distributions in water more alike. Highlighted in this work is the fact that some conventional specifications and methods for measurement of beam parameters such as penumbra are not relevant and further work is required to address this situation with respect to “matched” FFF beams and to determine methods of measurement that are not reliant on an associated flattened beam.

43 PARTICLE ACCELERATORS↗
DOE OSTI2020

Partner program with local college is a gateway to lasting careers

The first graduates of a newly revised associate degree program at Northern New Mexico College (NNMC) are starting their careers in radiation protection at the Laboratory. NNMC has long provided courses in radiation protection, but last year partnered with the Associate Laboratory Directorate of Weapons Production (ALDWP) to invigorate the college’s offerings.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2017

Release Report for Building Debris for TA-21 Sewage Treatment Facility

ENV-ES finds that the materials associated with TA-21 Buildings 227 (superstructure only), and 229 (see Figure 1) meet the criteria for unrestricted release to the public for recycle or as sanitary/commercial waste. The interior and exterior of the metal shed, building 387, passed the release criteria collectively; however, results from the roof of the structure were above reference background measurements. Waste management should be consulted for waste disposition options for the roofing metal. These findings are consistent with the requirements of DOE Order 458.1 “Radiation Protection of the Public and the Environment” and LANL Policy 412 “Environmental Radiation Protection.” Sampling and data analysis, as described in this report, were sufficient to meet measurement objectives under the Multi-Agency Radiation Survey and Assessment of Materials and Equipment (MARSAME) manual (2009).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Confirmation of Radiological Non-Impact Status for TA-37 Magazines

Environmental Protection and Compliance, Environmental Stewardship (EPC-ES) has evaluated radiological process knowledge and surveys and found that the structures and associated building materials in magazines at Technical Area 37 (TA-37) are candidates for unrestricted use and public release. TA-37 magazines included in this analysis are: buildings TA- 0006, -0008, -0009, -0019, and -0020. This finding is consistent with the requirements of DOE Order 458.1 Radiation Protection of the Public and the Environment and LANL Procedure FSD-004 Environmental Radiation Protection.

54 ENVIRONMENTAL SCIENCES↗