Hot Lab Research Articles

Future U.S. supply of Mo-99 production through fission based LEU/LEU technology.

Coquí RadioPharmaceuticals Corp. (Coquí) has the goal of establishing a medical isotope production facility for securing a continuous domestic supply of the radioisotope molybdenum-99 for U.S. citizens. Coquí will use an LEU/LEU proven and implemented open pool, light-water, 10 MW, reactor design. The facility is being designed with twin reactors for reliability an on-site hot lab chemical processing and a waste conditioning area and a possible generator producing radio-chemistry lab. Coquí identified a 25 acre site adjacent to an existing industrial park in northern central Florida. This land was gifted and transferred to Coquí by the University of Florida Foundation. We are in the process of developing licensing documents related to the facility. The construction permit application for submission to the U.S. Nuclear Regulatory Commission is currently being prepared. Submission is scheduled for mid to late 2015. Community reaction to the proposed development has been positive. We expect to create 220 permanent jobs and we have an anticipated to be operational by 2020.

Influence of six rejuvenators on the performance properties of Reclaimed Asphalt Pavement (RAP) binder and 100% recycled asphalt mixtures

100% recycled hot mix asphalt lab samples were modified with five generic and one proprietary rejuvenators at 12% dose and tested for binder and mixture properties. Waste Vegetable Oil, Waste Vegetable Grease, Organic Oil, Distilled Tall Oil, and Aromatic Extract reduced the Superpave performance grade (PG) from 94–12 of extracted binder to PG 64-22 while waste engine oil required higher dose. All products ensured excellent rutting resistance while providing longer fatigue life when compared to virgin mixtures and most lowered critical cracking temperature. Rejuvenated samples required more compaction energy compared to virgin and some oils reduced moisture resistance slightly.

Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs

The paper presents recent activities conducted at the Paul Scherrer Institut (PSI) in relation to the development and validation of an integral calculation methodology based on CASMO-4/SIMULATE-3/MCNPX for accurate estimations of the fast neutron fluence (FNF) accumulated on reactor pressure vessels and internals of the operating Swiss BWRs. With this computational scheme, the default neutron source is set up at the pin-by-pin level with realistic spectrum specifications based on the actual reactor cycle-specific data from validated reference CASMO-4/SIMULATE-3 core analysis models. On this basis, MCNPX models are then applied for optimized calculations of the fast neutron flux at the RPV or at any other location of interest including e.g. at surveillance dosimeters. In that framework, the validation studies conducted so far have included one dosimeter set irradiated in a BWR/6 reactor during two relatively recent operating cycles. Although this first analysis revealed a satisfactory performance when comparing the calculation results to measured data, it was considered necessary to proceed with further sensitivity/optimization studies combined with an enlarged validation basis (i.e. using additional dosimeter sets) in order to strengthen the overall confidence in the scheme both at the qualitative and quantitative level. A summary of the recent progress achieved in these directions is presented in this paper. To start, recalling that BWRs are characterized by very complex and heterogeneous fuel assembly and core designs (e.g. pins with different enrichments and burnable absorber loading, partial length rods, fuel assemblies of different types in the core), the impact of such heterogeneities on FNF estimations is under investigation in order to determine the level of modeling details required for accurate computational schemes to be used for long-term evaluations of modern BWR core designs. Next, additional validation studies based on experimental dosimeter data obtained from the same BWR/6 reactor are presented. These enlarged validation studies involve the analysis of four dosimeter sets, each irradiated during one cycle (including the 3 first reactor operation cycles), and subsequently analyzed at the PSI Hot Lab shortly after the dosimeters extraction. All these additional validation studies are conducted using both the JEFF-3.1.1 and the ENDF/B-VII.0 continuous-energy neutron data libraries in order to assess the sensitivity of the PSI BWR computational scheme also upon the employed nuclear data.

An evaluation of thickness effect in glycyrrihizic acid inside glycyrrhiza glabra root with compartion in several locations

Licorice is a self-propelling plant that has many applications in food, tobacco and pharmaceutical industries. Glycyrrhiza glabra is a kind of licorice whose main active constituents a triterpenoid saponin called glycyrrhizin. In this article we selected roots in three thickness sizes 0.4 to 1.5cm as s (small), 1.5 to 2.5cm as m (medium), 2.5 to 3.5cm as l (large) then roots were extracted with pressurized hot water extraction method inside Lab scale extractor (5 Liters) then evaporated and dried to analyze Glycyrrhizic acid content with HPLC.The results showed roots from all of locations are following this rule: more thickness, more Glycyrrhizic acid content such as in Afghanis, Uzbekistan, Turkey, Azerbaijan And Iran (7 areas) but we did not see similar slope for increasing glycyrrhizic acid against of thickness.

Central Nuclear Pharmacy, Our lost Treasure

Commercial central radiopharmacy is a mature and practical concept in the developed countries long time ago. However, in the developing ones where its importance and feasibility is much more valid, this concept is not yet well established. Since the running cost of nuclear medicine procedures is being considered the main obstacle of the NM progress in any developing country, it is clear that the central radiopharmacy can lead the NM progress and market in these countries(1).What is the central radiopharmacy? It is a highly specialized nuclear pharmacy which is able to produce and distribute calibrated, GMP complied and safe single radiopharmacetical doses to the NM facilities in its geographical area in a routine and scheduled timetables. A centralized nuclear pharmacy in any region having reasonable transportation facilities can lead to significant savings of money and personnel time. It must be shared by many, if not all, hospitals in a given region; otherwise it may not be feasible to run it economically. The scope of the central radiopharmacy Services can vary according to the capacity and needs of the served institutes. It can be assigned for PET and SPECT radiotracers or to only one of theses categories.What can a central radiopharmacy addto our nuclear medicine community?Cost Effectiveness It is well known to the NM practitioners that the main challenges in this field are not the initial investments on the machines, hot lab and radiation protection tools, but the running cost of radiopharmaceuticals and cold kits that are not usually complying with the number of patient procedures performed. The loss of Tc-99m activities that varies between 50% in busy institutes and 85% in low profile ones increase the cost of the NM procedures that limits the utilization of the NM technology due to this high cost in addition to the irregular availability of the tracers (Moly Crisis)(2). With the central radiopharmacy the cost can be reduced by up to 70% which will reduced the overall cost of the procedure what will encourage the referring physician to rely on the NM scans for their patients’ diagnosis.

Comment on: Somatostatin receptor SPECT

Comment on: Somatostatin receptor SPECT

Potential shielding for a positron emission tomography (PET) suite

Due to the amount of radioisotopes needed for use in positron emission tomography scans, it is important to have a careful planning of procedures and design of such facilities. Using the Monte Carlo N-Particle Transport Code (MCNP), a potential suite for a positron emission tomography (PET) facility was designed. The design covered three different areas as required in a PET facility: the scan room, the waiting area, and the hot lab. The design used two different shielding options, lead and concrete. Both materials were found to be enough to lower dose rates below the public dose limits set by the U.S. Nuclear Regulatory Commission.

Evaluation of Gd, Sm and Eu in Egyptian monazite samples using the prompt neutron capture gamma-ray technique

Three Egyptian monazite samples from the beach black sand at Abou Khashba near Rosetta, submitted by the laboratories of the nuclear materials authority of Egypt were analyzed for elemental contents, using Prompt gamma ray neutron activation analysis (PGNAA) as an effective analysis technique especially for rare earth elements. An integrated system for PGNAA, located at hot Lab. Center, has proven useful for the analytical purpose using 252Cf neutron source with neutron flux of 6.16E7 n/cm2 s, that system has been designed and calibrated for PGNAA. Sensitivity curves using different standard concentration values of artificial liquid standards samples at different concentrations ranging from 1,000 to 5,000 mg/L in case of Sm and Gd, while from 100 to 1,000 mg/L for Eu, have been constructed. The average concentration values for Gd, Sm and Eu in the samples under investigation was at 1.46E4 ± 0.21, 6.683E4 ± 0.14 and 440 ± 0.18 ppm, respectively. A comparative study of the obtained results and the results of ICP-Ms was given.

Song of the Secretary, Hot Lab

Song of the Secretary, Hot Lab

TH-SAMS-L100J-02: Shielding Design Workshop with Practical Problems II

The application of the structural shielding design techniques and goals as outlined in AAPM Task Group Report 108: PET and PET/CT Shielding Requirements Medical Physics (Vol. 33., Issue 1 (2006)) will be the basis for this practical course. Actual facility designs will be used as the example calculations of required shielding for PET/CT installations. As the use of PET and PET/CT units expands rapidly in the medical arena, the requirements for providing adequate radiation protection for both occupational personnel in these facilities and the public in uncontrolled areas around them necessitate the involvement of a qualified medical physicist. The many areas involved in implementing a PET/CT program including the Hot Lab, Patient Uptake Rooms, Patient Restrooms, Scan Rooms, and Disposal areas will be used as practical examples of typical structural shielding designs and evaluation methods. Educational Objectives: 1. Understand the exposure factors to be used for currently used PET isotopes to determine required structural shielding to meet exposure limits for occupational personnel and the public. 2. Understand the effectiveness of existing and additional structural shielding materials that provide radiation protection and methods to calculate the required amounts of these materials. 3. Understand the methods to be used in performing the shielding calculations of PET and PET/CT installations to insure adequate shielding to be provided to meet applicable state and ALARA requirements.

ＰＥＴセンターホットラボにおける線量率分布と従事者の被ばく線量低減の工夫

ＰＥＴセンターホットラボにおける線量率分布と従事者の被ばく線量低減の工夫

WE‐B‐330A‐01: Shielding Design Workshop: PET/CT

The application of the structural shielding design techniques and goals as outlined in AAPM Task Group Report 108: PET and PET/CT Shielding Requirements Medical Physics (Vol. 33., Issue 1 (2006)) will be the basis for this practical course. As the use of PET and PET/CT units expands rapidly in the medical arena, the requirements for providing adequate radiation protection for both occupational personnel in these facilities and the public in uncontrolled areas around them necessitate the involvement of a qualified medical physicist. The many areas involved in implementing a PET/CT program including the Hot Lab, Patient Uptake Rooms, Patient Restrooms, Scan Rooms, and Disposal areas will be used as practical examples of typical structural shielding designs and evaluation methods. The testing of PET shielding insures that the shielding is properly installed and that individuals do not exceed the radiation exposure levels required by applicable regulations and ALARA policies. Testing of PET and PET/CT shielding is a complex multidimensional problem since there are multiple sources and the radiation is emitted isotropically from the patients. Thus efficient testing can both save time and reduce radiation exposure to the physicists doing the testing. This course will discuss efficient methods for shielding testing. It will also review the instrumentation available to physicists for making the measurements. Practical methods of testing of a PET/CT facility will be presented.Educational Objectives:1. Understand the exposure factors to be used for currently used PET isotopes to determine required structural shielding to meet exposure limits for occupational personnel and the public.2. Understand the effectiveness of existing and additional structural shielding materials that provide radiation protection and methods to calculate the required amounts of these materials.3. Understand the methods to be used to evaluate the adequacy of PET and PET/CT installations to insure adequate shielding has been provided to meet applicable state and ALARA requirements.

Sci‐AM Fri ‐ 05: Shielding design for a PET‐CT simulator in a radiotherapy department

Purpose: To design the shielding for a PET‐CT simulator in a radiation therapy department, and to verify the adequacy of shielding during acceptance testing. Method and Materials: A Discovery ST (GE Healthcare, Milwaukee, USA) PET‐CT scanner replaced a CT‐Simulator in our centre. Existing space was reconfigured to include a patient rest area for FDG uptake and a hot lab. Adjacent areas included a simulator control room, patient waiting rooms, and corridors; floors above and below contained offices and linac bunkers and control rooms. Patients were modeled as point sources; attenuation by concrete walls and lead shielding explicitly included build‐up. Design limits were set to 1 mSv per year for nuclear energy workers (NEWs), and 0.05 mSv per year for non‐NEWs. A linear 1.5‐GBq source of in scattering material was used to verify the adequacy of the shielding. Results: The control room was shielded with 6.35 mm of Pb. Two sheets of lead glass (48% Pb by weight) totaling 14 mm provided sufficient attenuation for a window. The patient uptake area and the scanner room were shielded with 4.7 mm of Pb on walls adjacent to corridors. No shielding was required on the floor and ceiling. Measurement showed that design goals were met. Conclusion: Strategic location of patients, NEWs, and low‐occupancy areas simplified design to these stringent limits. Careful consideration of workloads and occupancy factors are needed to meet the design criteria, particularly when older facilities are being redesigned. Design to such low limits unnecessarily increases construction cost.

An efficient negative surface ionization source for RIB generation

A high-efficiency, negative surface ionization source, equipped with spherical-sector LaB 6 ionizer, has been developed for generating radioactive beams of highly electronegative species for accelerator-based nuclear physics and nuclear astrophysics research. The source utilizes direct-surface ionization to form negative-ion beams resulting from interactions between highly electronegative atoms or molecules and a hot (∼1722 °C) LaB 6 surface. Even though this type of ionizer has a widely publicized propensity for being easily poisoned, no evidence of this effect was experienced during testing of the source. The source has been extensively evaluated off-line in terms of ionization efficiency for generating beams of Cl − and Br − by feeding AlCl 3 and AlBr 3 vapors at low-feed rates into the source. The geometry of the ionization volume is designed to minimize direct losses of neutral particles through the extraction aperture and to enhance the probability for striking the LaB 6 ionizer. The source is reliable, stable and easy to operate, and ionizes Cl − and Br − with efficiencies for formation and extraction of 30% and 20%, respectively. The design features, principles of operation, off-line performance, operational-parameter and beam-quality (emittance) data for the source are presented in this article.

NET NEWS: Calling All Microarray Data

Researchers who've joined the stampede to use glass chips dotted with specks of genes to study how cells work now have a place to share their growing piles of data. Last week, the National Center for Biotechnology Information (NCBI) rolled out a new Web database that will archive results from DNA microarrays and other hot lab tools for seeing the expression of thousands of genes at once.

Solving difficult site problems for MRI and PET

Many of our most sophisticated hospitals are located in urban areas where available land is at a minimum. Consequently ideal sites for diagnostic equipment like PET, medical cyclotrons, and MRI scanners are not available. These sites require special structural considerations, shielding provisions, and construction access. Due to the processes involved in PET and MRI scanning, shielding for radiation, radio frequency, and magnetic fields are required in order to protect adjacent functions. The process of evaluating potential sites and coordinating the design and construction requires a higher degree of planning, management, and technical considerations in order to succeed. The challenge is then to handle these difficult project aspects as well is all of the normal design considerations. Project teams often involve administration, physicians, physicists, hot lab technicians, equipment manufacturers, architects, and engineers and must be well coordinated in order to solve all of the design and technical issues. The process described here has been developed through a series of project efforts. Included in this discussion are two sample projects from our work at the University of Pittsburgh Medical Center.

'Hot lab' to be closed over contamination fears

'Hot lab' to be closed over contamination fears