Nuclear Technology Reivew for 2002
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小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
Trends Towards Sustainability in the Nuclear Fuel Cycle
Nuclear Development 2011 Trends towards Sustainability in the Nuclear Fuel Cycle Executive Summary NUCLEAR ENERGY AGENCY Nuclear Development Trends towards Sustainability in the Nuclear Fuel Cycle Executive Summary Full publication available at: www.oecdbookshop.org © OECD 2011 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Executive summary Over the last decade, there has been increased recognition of the role that civil nuclear power could play in terms of energy security and greenhouse gas reductions, especially if viewed over the long time frames of the expected lifetimes of current reactor technology. Nuclear energy presents a number of attractive features: it generates essentially no greenhouse gas emissions during production (limiting climate change) and no air pollution (avoiding very detrimental health effects); it is largely immune to the intermittency and unpredictability exhibited by wind and solar energy; it uses fuels with very high energy density (easing the establishment of significant strategic stockpiles) with resources and fabrication facilities distributed in diverse and (mostly) geopolitically stable countries. It therefore contributes to security of supply and offers a reliable energy source for countries where demand for electricity is growing rapidly. Such countries, including China and India, have thus been pursuing rapid deployment of nuclear energy and related fuel cycle elements, including reprocessing and recycling. Nuclear energy can be economically competitive, especially if carbon pricing is considered and financing costs are controlled. Certainly the sector still faces a number of challenges: first and foremost the requirement for continuous enhancement of safety and safety culture (reinforced in particular by the accidents of Three Mile Island, Chernobyl and the more recent accident at Fukushima Daiichi), the need to control the spread of technologies and materials that may be used for non-peaceful purposes and to implement final solutions for radioactive waste disposal and management. -
Radioactive Seed Localization of Breast Lesions: an Adequate Localization Method Without Seed Migration
ORIGINAL ARTICLE Radioactive Seed Localization of Breast Lesions: An Adequate Localization Method without Seed Migration Tanja Alderliesten, PhD,* Claudette E. Loo, MD,* Kenneth E. Pengel, MSc,* Emiel J. Th. Rutgers, MD, PhD, Kenneth G. A. Gilhuijs, PhD,* and Marie-Jeanne T. F. D. Vrancken Peeters, MD, PhD *Department of Radiology; and Department of Surgery, The Netherlands Cancer Institute – Antoni van Leeuwenhoek Hospital (NKI-AVL), Amsterdam, The Netherlands n Abstract: Preoperative localization is important to optimize the surgical treatment of breast lesions, especially in nonpal- pable lesions. Radioactive seed localization (RSL) using iodine-125 is a relatively new approach. To provide accurate guid- ance to surgery, it is important that the seeds do not migrate after placement. The aim of this study was to assess short-term and long-term seed migration after RSL of breast lesions. In 45 patients, 48 RSL procedures were performed under ultrasound or stereotactic guidance. In the first 12 patients, the lesion was localized with two markers: an iodine-125 seed and a refer- ence marker. In 33 patients, 36 RSL procedures were performed using a single iodine-125 seed. All patients received control mammograms after seed placement and prior to surgery. In the patients with two markers, migration was defined as the differ- ence in the largest distance between the markers observed in the mammograms. For single-marked lesions, migration was assessed by comparing distances between anatomical landmarks in the mammograms. RSL was successful in all patients. Seeds were in-situ for 59.5 days on average (3–136 days). The detection rate during surgery was 100%. -
Nuclear Reprocessing and Proliferation: Alternative Approaches and Their Implications for the Federal Budget
BACKGROUND PAPER Nuclear Reprocessing and Proliferation: Alternative Approaches and their Implications for the Federal Budget May 1977 Congress of the United States Congressional Budget Office Washington, D.C. NUCLEAR REPROCESSING AND PROLIFERATION: ALTERNATIVE APPROACHES AND THEIR IMPLICATIONS FOR THE FEDERAL BUDGET The Congress of the United States Congressional Budget Office For sale by the Superintendent of Documents, U.S. Government Printing OfBce Washington, D.C. 20402 NOTE The Congressional Budget Office has prepared seven other studies on topics related to energy. Copies of these reports can be obtained through CBO's Office of Intergovernmental Relations or, through the U.S. Government Printing Office. Their titles are as follows: Commercialization of Synthetic Fuels: Alternative Loan Guarantee and Price Support Programs Background Paper No. 3 Uranimum Enrichment; Alternatives for Meeting the Nation's Needs and Their Implications for the Federal Budget Background Paper No. 7 GPO Stock No. 052-070-03367-3 Energy Research: Alternative Strategies for Development of New Federal Energy Technologies and Their Implications for the Federal Budget Background Paper No. 10 GPO Stock No. 052-070-03510-2 Financing Energy Development Background Paper No. 12 GPO Stock No. 052-070-03542-1 Petroleum Storage; Alternative Programs and Their Implications for the Federal Budget Background Paper No. 14 GPO Stock No. 052-070-03718-1 Energy Research. Development, Demonstration, and Commercialization Budget Issue Paper GPO Stock No. 052-070-03890-0 Energy Policy Alternatives Budget Issue Paper GPO Stock No. 052-070-03912-4 PREFACE Nuclear Reprocessing and Proliferation analyses and provides background information on the relationship between reprocessing of spent nuclear fuel and the proliferation of nuclear weapons. -
Intraoperative Gamma Probe Detection of Bone Invasive
Intraoperative and Postoperative Gamma Detection of Somatostatin Receptors in Bone Invasive “En Plaque” Meningiomas Emmanuel GAY, MD; Jean Philippe VUILLEZ, MD, PhD; Olivier PALOMBI, MD; Pierre Yves BRARD, MD; Pierre BESSOU, MD and Jean Guy PASSAGIA, MD. Department of Neurosurgery (EG, OP, JGP), Department of Nuclear Medecine (JPhV, PYB) and Departement of Neuroradiology (PB), University Hospital Grenoble, France. This is a non-final version of an article published in final form in Neurosurgery: July 2005 - Volume 57 - Issue 1 - pp 107-113 E. GAY Corresponding author: Emmanuel GAY, MD Department of Neurosurgery (Pr A.L. Benabid) CHU Grenoble BP217 38043 Grenoble Cedex 09 FRANCE Tel: 33 476 76 54 71 Fax: 33 476 76 58 13 Email: [email protected] 2 E. GAY Intraoperative and Postoperative Gamma Detection… Abstract: Objective: Scintigraphy with radiolabeled somatostatin analogue ([111In-DTPA] octreotide), detects the somatostatin receptors that are found in vitro in all meningiomas. Previous studies have proved the benefit of radioimmunoguided surgery with a handheld gamma probe, for the assessment and the removal of neuroendocrine tumors. We conducted a study to determine whether intraoperative radiodetection of somatostastin receptors is feasible and could increase the probability of complete meningioma resection, especially for bone invasive “en plaque” meningiomas that are difficult to control surgically. Methods: Eighteen patients with “en plaque” sphenoid wing and skull convexity meningiomas were studied for pre and post-operative somatostatin receptor scintigraphy. In 10 of them, intraoperative radiodetection using a handheld gamma probe was performed 24 hours after the intravenous administration of [111In-DTPA] octreotide. This procedure was combined with a computer-aided navigation system. -
Hybrid K-Edge Densitometry As a Method for Materials Accountancy Measurements in Pyrochemical Reprocessing
University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Doctoral Dissertations Graduate School 5-2015 Hybrid K-edge Densitometry as a Method for Materials Accountancy Measurements in Pyrochemical Reprocessing Matthew Tyler Cook University of Tennessee - Knoxville, [email protected] Follow this and additional works at: https://trace.tennessee.edu/utk_graddiss Part of the Nuclear Engineering Commons Recommended Citation Cook, Matthew Tyler, "Hybrid K-edge Densitometry as a Method for Materials Accountancy Measurements in Pyrochemical Reprocessing. " PhD diss., University of Tennessee, 2015. https://trace.tennessee.edu/utk_graddiss/3329 This Dissertation is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Doctoral Dissertations by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a dissertation written by Matthew Tyler Cook entitled "Hybrid K-edge Densitometry as a Method for Materials Accountancy Measurements in Pyrochemical Reprocessing." I have examined the final electronic copy of this dissertation for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Doctor of Philosophy, with a major in Nuclear Engineering. Steven E. Skutnik, Major Professor We have read this dissertation and recommend its acceptance: Howard L. Hall, Joseph R. Stainback, Lawrence Heilbronn, James Ostrowski Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) Hybrid K-edge Densitometry as a Method for Materials Accountancy Measurements in Pyrochemical Reprocessing A Dissertation Presented for the Doctor of Philosophy Degree The University of Tennessee, Knoxville Matthew Tyler Cook May 2015 c by Matthew Tyler Cook, 2015 All Rights Reserved. -
(EANM) Acceptance Testing for Nuclear Medicine Instrumentation
Eur J Nucl Med Mol Imaging (2010) 37:672–681 DOI 10.1007/s00259-009-1348-x GUIDELINES Acceptance testing for nuclear medicine instrumentation Ellinor Busemann Sokole & Anna Płachcínska & Alan Britten & on behalf of the EANM Physics Committee Published online: 5 February 2010 # EANM 2010 Keywords Quality control . Quality assurance . requirement that acceptance testing be performed should Acceptance testing . Nuclear medicine instrumentation . be included in the purchase agreement of an instrument. Gamma camera . SPECT. PET. CT. Radionuclide calibrator. This agreement should specify responsibilities regarding Thyropid uptake probe . Nonimaging intraoperative probe . who does acceptance testing, the procedure to be followed Gamma counting system . Radiation monitors . when unsatisfactory results are obtained, and who supplies Preclinical PET the required phantoms and software. A specific time slot must be allocated for performing acceptance tests. Introduction Acceptance and reference tests These recommendations cover acceptance and reference tests that should be performed for acceptance testing of Acceptance tests are performed to verify that the instrument instrumentation used within a nuclear medicine department. performs according to its specifications. Each instrument is These tests must be performed after installation and before supplied with a set of basic specifications. These have been the instrument is put into clinical use, and before final produced by the manufacturer according to standard test payment for the device. These recommendations -
Plutonium and China's Future Nuclear Fuel Cycle Jasper Pandza, International Institute for Strategic Studies [email protected]
1 Plutonium and China’s Future Nuclear Fuel Cycle Jasper Pandza, International Institute for Strategic Studies [email protected] 13th PIIC Beijing Seminar on International Security: Building a World of Sustainable Peace and Stability Beijing, China October 31 - 3 November, 2012 Introduction Following the March 2011 Fukushima accident, the State Council, China’s highest policy- making body, suspended approvals for new nuclear plants and initiated a range of other measures aimed at improving the country’s nuclear safety provisions. The suspension of new construction approvals is expected to be lifted within the coming months,1 after being in place for longer than initially expected. The State Council’s actions demonstrated a new resolve among China’s leadership to give nuclear safety considerations greater priority compared to the economic benefits of nuclear power. The Fukushima accident apparently gave policy makers a reason to fear that a similar accident in China would put the government-run nuclear programme at serious risk. Throughout the past year, China has not moved away from its long-standing commitment to a closed, plutonium-based nuclear fuel cycle with spent fuel reprocessing and fast-neutron reactors. However, China’s response to Fukushima appears to have delayed progress in that direction. The construction of conventional light water reactors (LWR) will soon gather greater pace, but further delays in China’s fuel-cycle plans can be expected, as resources may need to be diverted towards improving the safety of current and future LWRs and to accelerating the shift from generation II to generation III LWR technology. This cautious approach should be welcomed, because it provides China with further opportunity to reconsider the economic rationale and the security risks associated with reprocessing and fast-reactor technologies. -
Paper RADIOACTIVE SEED LOCALIZATION with I for NONPALPABLE LESIONS PRIOR to BREAST LUMPECTOMY AND/OR EXCISIONAL BIOPSY
Paper RADIOACTIVE SEED LOCALIZATION WITH 125I FOR NONPALPABLE LESIONS PRIOR TO BREAST LUMPECTOMY AND/OR EXCISIONAL BIOPSY: METHODOLOGY, SAFETY, AND EXPERIENCE OF INITIAL YEAR Lawrence T. Dauer,*† Cynthia Thornton,† Daniel Miodownik,* Daniel Boylan,* Brian Holahan,* Valencia King,‡ Edi Brogi,§ Monica Morrow,** Elizabeth A. Morris,† and Jean St. Germain* INTRODUCTION AbstractVThe use of radioactive seed localization (RSL) as an alternative to wire localizations (WL) for nonpalpable breast IMPROVEMENTS IN imaging techniques and increasing rates lesions is rapidly gaining acceptance because of its advantages of screening mammograms have resulted in the increased for both the patient and the surgical staff. This paper exam- ines the initial experience with over 1,200 patients seen at a detection of nonpalpable breast lesions that require locali- comprehensive cancer center. Radiation safety procedures for zation prior to surgery to allow excision for complete his- radiology, surgery, and pathology were implemented, and ra- tological evaluation or as part of breast-conserving therapy dioactive material inventory control was maintained using an (Harris et al. 1981; Homer 1983; Cady et al. 1996; Montrey intranet-based program. Surgical probes allowed for discrimina- tion between 125I seed photon energies from 99mTc administered for et al. 1996; Bartelink et al. 2001; Skinner et al. 2001; Hooley sentinel node testing. A total of 1,127 patients (median age et al. 2012; Nederend et al. 2012). Breast image-guided of 57.2 y) underwent RSL procedures with 1,223 seeds im- localization is performed on nonpalpable lesions after Y planted. Implanted seed depth ranged from 10.3 107.8 mm. marker clips are left in the breast following image-guided The median length of time from RSL implant to surgical excision was 2 d. -
Radioactive Materials Transportation and Incident Response
RADIOACTIVE MATERIALS TRANSPORTATION AND INCIDENT RESPONSE U.S. Department of Energy Transportation Emergency Preparedness Program Q&A About Incident Response 04/12 QA Phone Number Radio Frequency Law Enforcement ____________________________________ RADIOACTIVE Fire ___________________________________________ MATERIALS Medical ____________________________________________ TRANSPORTATION AND INCIDENT RESPONSE State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______ CHEMTREC (Outside US) 1-703-527-3887 ________________ National Response Center (Toll-free US & Canada) 1-800-424-8802 ____________ In Washington, D.C. 1-202-267-2675 _____________________ Military Shipments (DoD) Call Collect 1-703-697-0218 _______ Other: ______________________________________________ Other: ______________________________________________ QQ&A About Incident Response NOTES TABLE OF CONTENTS What is radiation?.................................................................................... 2 ______________________________________________ What is radiation exposure? .................................................................... 3 ______________________________________________ -
Nuclear High-Level Waste Tank Explosions: Potential Causes and Impacts of a Hypothetical Accident at India's Kalpakkam Repro
SCIENCE & GLOBAL SECURITY ,VOL.,NO.,– http://dx.doi.org/./.. Nuclear High-level Waste Tank Explosions: Potential Causes and Impacts of a Hypothetical Accident at India’s Kalpakkam Reprocessing Plant M. V. Ramana, A. H. Nayyar, and Michael Schoeppner Program on Science and Global Security, Princeton University, Princeton, NJ, USA ABSTRACT ARTICLE HISTORY Tanks holding liquid high level waste from reprocessing spent Received July fuel have large inventories of highly radioactive materials. These Accepted July tanks could potentially be damaged by a variety of chemical explosions, leading to the dispersion of a significant fraction of their radioactive contents. This article describes some of the dif- ferent chemical explosions that could occur and examines how such explosions could occur at the Kalpakkam Reprocessing Plant in India, which likely stores a large volume of high level liq- uid waste because vitrification of that waste did not begin until more than 15 years after the plant began operating in 1998. The atmospheric dispersion of the hypothetical radioactive release is modeled using the Hybrid Single-Particle Lagrangian Integrated Trajectory Model developed by the Air Research Laboratory of the U.S. National Oceanic and Atmospheric Administration. The results suggest that the modeled accident scenario would lead to nearly 97,000 cancers, with roughly 47,000 of these being fatal. Larger radioactive releases are possible and would lead to propor- tionately higher incidence of cancer and cancer-caused mortality. Introduction Reprocessing -
Reprocessing of Spent Nuclear Fuel
Reprocessing of spent nuclear fuel Jan Willem Storm van Leeuwen independent consultant member of the Nuclear Consulting Group November 2019 [email protected] Note In this document the references are coded by Q-numbers (e.g. Q6). Each reference has a unique number in this coding system, which is consistently used throughout all publications by the author. In the list at the back of the document the references are sorted by Q-number. The resulting sequence is not necessarily the same order in which the references appear in the text. reprocessing20191107 1 Contents Roots of reprocessing Once-through and closed-cycle systems Reprocessing of spent nuclear fuel Reprocessing and the Second Law Separation Purification Reprocessed uranium Plutonium Neptunium-237 Americium MOX fuel in LWRs Destruction of HEU and Pu: burning the Cold War legacy Uranium-plutonium breeder systems Reprocessing of FBR fuel Thorium for fission power Uranium-233 Molten-salt reactor Partitioning and transmutation Nuclear terrorism Vitrification Discharges Entropy generation by reprocessing Concluding notes References TABLES Table 1 Reprocessing plants world-wide Table 2 Discharges of radionuclides in the liquid and gaseous effluents of a reprocessing plant Table 3 Discharge limits of reprocessing plants to the sea Table 4 Discharge limits of reprocessing plants at La Hague FIGURES Figure 1 Mass composition of fresh and spent nuclear fuel Figure 2 Mass flows of reprocessing Figure 3 Outline of plutonium recycling in LWRs Figure 4 Outline of uranium-plutonium breeder cycle Figure 5 Principle of a partitioning and transmutation system Figure 6 Redistribution of the radioactive contents of spent fuel by reprocessing Figure 7 Symbolic representation of the entropy production by reprocessing reprocessing20191107 2 Roots of reprocessing Reprocessing technology has been developed during the late 1940s and during the Cold War to recover plutonium from spent fuel from special military reactors for the production of nuclear weapons.