WorldWideScience

Sample records for clandestine nuclear testing

  1. Multi-Use Seismic Stations Offer Strong Deterrent to Clandestine Nuclear Weapons Testing

    OpenAIRE

    Hennet, C. B.; van der Vink, G. E.; Richards, P.G.; Adushkin, V. V.; Kopnichev, Y. F.; Geary, R.

    1996-01-01

    As the United States and other nations push for the signing of a Comprehensive Test Ban Treaty, representatives are meeting in Geneva this year to develop an International Seismic Monitoring System to verify compliance with the treaty's restrictions. In addition to the official monitoring system, regional networks developed for earthquake studies and basic research can provide a strong deterrent against clandestine testing. The recent release of information by the U.S. Department of Energy (D...

  2. Detecting clandestine material with nuclear resonance fluorescence

    Science.gov (United States)

    Pruet, J.; McNabb, D. P.; Hagmann, C. A.; Hartemann, F. V.; Barty, C. P. J.

    2006-06-01

    We study the performance of a class of interrogation systems that exploit nuclear resonance fluorescence (NRF) to detect specific isotopes. In these systems the presence of a particular nuclide is inferred by observing the preferential attenuation of photons that strongly excite an electromagnetic transition in that nuclide. Estimates for the false positive/negative error rates, radiological dose, and detection sensitivity associated with discovering clandestine material embedded in cargo are presented. The relation between performance of the detection system and properties of the beam of interrogating photons is also considered. Bright gamma-ray sources with fine energy and angular resolution, such as those based on Thomson upscattering of laser light, are found to be associated with uniquely low radiological dose, scan times, and error rates. For this reason a consideration of NRF-based interrogation systems may provide impetus for efforts in light source development for applications related to national security and industry.

  3. Environmental Detection of Clandestine Nuclear Weapon Programs

    Science.gov (United States)

    Kemp, R. Scott

    2016-06-01

    Environmental sensing of nuclear activities has the potential to detect nuclear weapon programs at early stages, deter nuclear proliferation, and help verify nuclear accords. However, no robust system of detection has been deployed to date. This can be variously attributed to high costs, technical limitations in detector technology, simple countermeasures, and uncertainty about the magnitude or behavior of potential signals. In this article, current capabilities and promising opportunities are reviewed. Systematic research in a variety of areas could improve prospects for detecting covert nuclear programs, although the potential for countermeasures suggests long-term verification of nuclear agreements will need to rely on methods other than environmental sensing.

  4. Clandestine nuclear trade and the threat of nuclear terrorism

    International Nuclear Information System (INIS)

    The nuclear netherworld may ultimately contribute to the danger of nuclear terrorism in at least three ways. First, as national governments exploit this underground market and nuclear weapons spread to additional states, the possibility that terrorists will gain access to them will grow. Such weapons in nuclear threshold countries are likely to be more vulnerable to terrorist seizure than they are in today's more advanced nuclear weapons states. Second, terrorist groups might seek to exploit the nuclear gray market themselves, using the same subterfuges that national governments use. Although in today's nuclear netherworld, subnational groups cannot obtain nuclear arms or nuclear weapons material and cannot hope to build the complex installations needed to produce the latter, they might be able to engage in a form of barter with sympathetic emerging nuclear states (for example, offering raw materials or needed nuclear hardware in return for nuclear weapons material. Finally, there is always the risk that nuclear arms or nuclear weapon materials will someday become available on the nuclear black market. There is evidence indicating that terrorist organizations might well be interested in acquiring such items. Understanding underground nuclear commerce in its current form is essential to prevent such future dangers

  5. Hand-Held Devices for the Detection of Clandestine Nuclear Material on Site

    International Nuclear Information System (INIS)

    The potential threat of nuclear material out of legal control has become an increasingly important issue for the international community in the last years. Improvised Nuclear Devices (IND) and Dirty Bombs may have far reaching consequences, e.g., contaminating vast areas and even killing people, when successfully detonated by terrorists or terrorist groups. Whereas the declared nuclear material in the nuclear fuel cycle is under good control by international safeguards it is difficult to cope with undeclared or stolen nuclear material. The best detectors and sophisticated methods have to be used to reveal undeclared as well as clandestine nuclear material or activities. Important means for detecting such material are portal monitors and other fixed installations at state boarders and gateways of nuclear and industrial facilities. In addition mobile measuring systems are of great importance. These fixed installations and mobile measuring systems have to be supplemented by reliable and easy to use hand-held devices for the detection of gamma and neutron radiation emitted by the material. Hand-held devices may not only be used in combination with fixed installations and mobile systems but may also support police men or fire fighters to detect illicit radioactive and nuclear material. We tested a variety of advanced hand-held devices with respect to reliability, ease of use, quality of the user interface, false alarm rate and the generation of wrong results. Another important issue is the necessary skill and operating experience of the operational staff in their work. As many users will not be specialist in the area of measurement of radiation the utilization of hand-held devices must be simple and to a great extend fool proof. In this respect we investigated gamma dosimeters and pagers as well as spectroscopic devices, gamma detection systems equipped additionally with a small neutron detector and dedicated neutron devices also. Hand-held devices are an inevitable

  6. Simulation of atmospheric krypton-85 transport to assess the detectability of clandestine nuclear reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Ross, Jens Ole

    2010-02-02

    The radioactive noble gas krypton-85 is released into the atmosphere during reprocessing of spent nuclear fuel or irradiated breeding targets. This is a necessary step for plutonium separation. Therefore the {sup 85}Kr signature of reprocessing could possibly be used for the detection of undeclared nuclear facilities producing nuclear weaponusable material. The {sup 85}Kr content of the atmosphere has grown over the last decades as the emissions from military and civilian nuclear industry could not be compensated by the decay with a half-life of 10.76 years. In this study, the global {sup 85}Kr background distribution due to emissions of known reprocessing facilities for the period from 1971 until 2006 was simulated using the atmospheric general circulation model ECHAM5 applying the newest available annual emission data. The convective tracer transport scheme and the operator splitting for the physical calculations in the model were modified in order to guarantee physically correct results for tracer point sources, in particular non negative concentrations. An on-line routine controlling the {sup 85}Kr -budget in the model enforced exact mass conservation. The results of the simulation were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection with very good agreement at most observation sites except those in the direct vicinity of {sup 85}Kr sources. Of particular interest for the {sup 85}Kr detection potential was the variability of {sup 85}Kr background concentrations which was evaluated for the first time in a global model. In addition, the interhemispheric transport as simulated by ECHAM5 was analyzed using a two-box model providing a mean exchange time of τ {sub ex} = 10.5 months. The analysis of τ{sub ex} over simulated 35 years indicates that in years with strong South Asian or African Monsoon the interhemispheric transport is faster during the monsoon season. A correlation analysis of

  7. Nuclear stress test

    Science.gov (United States)

    ... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

  8. Change Detection for Remote Monitoring of Underground Nuclear Testing: Comparison with Seismic and Associated Explosion Source Phenomenological Data

    OpenAIRE

    Canty, M.; G. Jahnke; Nielsen, Allan Aasbjerg; Schlittenhardt, J.

    2005-01-01

    The analysis of open-source satellite imagery is in process of establishing itself as an important tool for monitoring nuclear activities throughout the world which are relevant to disarmament treaties, like e. g. the Comprehensive Nuclear-Test-Ban Treaty (CTBT). However, the detection of anthropogenic changes associated with underground nuclear activities, whether declared or clandestine, presents a difficult challenge, since it is necessary to discriminate subtle, often weak signals of inte...

  9. On-site inspection: A brief overview and bibliography of techniques pertinent to assessing suspected nuclear test sites

    International Nuclear Information System (INIS)

    The purpose of this report is to provide a brief overview and bibliography of those techniques that may have application for the evaluation of a site to determine if a high energy release event is nuclear in nature. This effort is motivated by recognition of the changing world political climate and the perception that low yield and non-proliferation issues will grow in importance as countries become increasingly involved as signators to treaties that are intended to limit the development and testing of nuclear weapons. Along with an increasing interest in such issues is the awareness of the need to implement improved capabilities for treaty monitoring programs that must deal with assessing suspicious occurrences of high energy release events. In preparing this report, it is recognized that monitoring can take two main forms. The first involves the resolution of unidentified events detected by seismic and satellite National Technical Means. Events of an indeterminate nature could occur world-wide and could induce tension in neighboring countries. If an on-site measurement capability were available, a monitoring team could be sent to the suspected site of an event to take measurements that could confirm or disprove the occurrence of a clandestine nuclear test. The second monitoring form is the confirmation that a clandestine event is not masked by a declared event. For example, a large mining explosion could mask a decoupled nuclear explosion. On-site measurements before and during the test could confirm that a clandestine event did not occur and could provide assurance that the party carrying out the explosion is not taking advantage of clandestine testing opportunities. 48 refs

  10. A comprehensive ban on nuclear testing.

    Science.gov (United States)

    Neild, R; Ruina, J P

    1972-01-14

    means now available for verification. 4) It will become increasingly difficult in the United States to oppose the CTB on the basis of risks that accompany possible Soviet evasion of a treaty that does not include the right of onsite inspection. The opposition to a CTB is now likely to shift to the more direct argument that nuclear testing is important to keep pace with continuing worldwide technical and military developments. The justification for U.S. testing is only in part because of advances in Soviet nuclear technology per se. Those opposing a CTB may argue that it makes little sense, and may even be courting danger, to freeze nuclear technology alone and that banning nuclear tests should await an agreement that copes with all military research and development and all qualitative improvements in weapons systems. This directly confronts the argument that the unique virtue of a CTB is that it provides a simple and feasible first step in the very complicated problems of controlling military technology. 5) The mutual deterrence of the superpowers will not be compromised if a CTB agreement is reached and one side or the other clandestinely violates such an agreement. The state of nuclear technology in both countries is mature, and the destructive capability of their nuclear arsenals can be easily maintained. Whatever small improvements can come as a consequence of clandestine testing would hardly affect the strategic balance. 6) It seems unlikely that China and France will agree to stop testing in the near future. These countries refused to join the nonproliferation treaty, which did not affect their nuclear programs, and it is doubtful that, proceeding from military considerations alone, they would join a CTB. Their nuclear programs are still not mature, and a CTB would freeze their positions of inferiority with respect to the superpowers. There may, however, be wider political and security arrangements to induce them to participate. Cessation of tests by the other

  11. The nuclear test-ban verification regime: An untapped source for climate change monitoring

    International Nuclear Information System (INIS)

    The benefits of a global ban on nuclear testing for international security and for protecting human health and the environment from radioactive fallout are obvious. The relevance of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) for climate change research may not, however, be evident at first glance. The CTBT bans all nuclear explosions on Earth. To monitor compliance with the Treaty, the CTBTO Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), is establishing a verification regime capable of detecting clandestine nuclear tests. As the only international body operating its own system of monitoring stations that literally spans the globe, the CTBTO is in a unique position to contribute to the UN's efforts in the area of climate knowledge.

  12. Detection of clandestine activities: a global approach

    International Nuclear Information System (INIS)

    The detection of clandestine activities is mainly a question of global approach, dealing with all the steps of the proliferation process. The detection of clandestine activities could be achieved adopting a four step global approach. First, you have to perfectly know the fuel and weapons cycles. Then, you have to be able to describe all the indicators and signatures of those cycles. Once those indicators are known, you need to detect them through the use of the right sensors that could be either technical sensors but also other 'sensors' like export control, visa control and other tools like bibliometry. When all information is available, there is a need for data mining and data fusion including also all open source information. The paper is followed by the slides of the presentation

  13. Decades of nuclear testing

    International Nuclear Information System (INIS)

    The United States carried out the world's first nuclear test in 1945. The test marked the beginning of an arms race between the great powers that lasted for decades. Innumerable nuclear test explosions were detonated to test and refine the weapons. The arms race picked up speed in the 1950s and culminated in 1958, when the United States detonated 77 and the Soviet Union 35 nuclear explosions. This was followed by the first pause in nuclear testing, brought about through the efforts of the Pugwash organisation consisting of the world's foremost scientists. Finland, too, received its share of the radioactive fallout coming from atmospheric nuclear explosions. Rain water samples have been studied for radioactivity in Finland since the mid-1950s. The first studies to determine the internal radiation doses caused by radioactive substances in man were conducted in the late 1950s by measuring cesium and strontium contents in grass and in milk. The efficiency of research and radiation monitoring improved in the 1960s, which was also a time when training in the sector developed rapidly. In consequence, when the accident in Chernobyl took place Finland had already gained valuable experience needed for rapid determination of unexpected fallout. (orig.) (3 figs.)

  14. On site inspection for nuclear test ban verirication

    Directory of Open Access Journals (Sweden)

    P. D. Marschall

    1994-06-01

    Full Text Available The problem of verifying compliance with a nuclear test ban treaty is mainly a technical one. However the problem of detecting, locating and identifying nuclear explosions has, since the late 1950s, been intimately involved with the political problems associated with negotiating a treaty. In fact there are few other areas in which policy, diplomacy and science have been so interwoven. This paper attempts to illustrate how technology can. be applied to solve some of the political problems which arise when considering the role of an On Site Inspection (OSI to determine whether or not a nuclear explosion, in violation of a treaty, has occurred or not. It is hoped that the reader, with a scientific background, but with little or no experience of treaty negotiations, will gain an. insight as to how technical matters can interact with political requirements. The demands made on scientists to provide technical support for negotiating and rnonitoring compliance of a treaty have increased significanfly over the last 40 years. This is a period in which a number of major treaties have contained a significant technical component e.g. the Limited Test Ban Treaty (Threshold Treaty and the Chemical Weapon Convention. This paper gives an indication of some of the political decisions which will have to be made and suggests some of the technical methods which are of value in the identification of a clandestine nuclear explosion.

  15. Experiments to Detect Clandestine Graves from Interpreted High Resolution Geophysical Anomalies

    Science.gov (United States)

    Molina, C. M.; Hernandez, O.; Pringle, J.

    2013-05-01

    This project refers to the search for clandestine sites where possibly missing people have been buried based on interpreted near surface high resolution geophysical anomalies. Nowadays, there are thousands of missing people around the world that could have been tortured and killed and buried in clandestine graves. This is a huge problem for their families and governments that are responsible to warranty the human rights for everybody. These people need to be found and the related crime cases need to be resolved. This work proposes to construct a series of graves where all the conditions of the grave, human remains and related objects are known. It is expected to detect contrasting physical properties of soil to identify the known human remains and objects. The proposed geophysical methods will include electrical tomography, magnetic and ground penetrating radar, among others. Two geographical sites will be selected to located and build standard graves with contrasting weather, soil, vegetation, geographic and geologic conditions. Forward and inverse modeling will be applied to locate and enhance the geophysical response of the known graves and to validate the methodology. As a result, an integrated geophysical program will be provided to support the search for clandestine graves helping to find missing people that have been illegally buried. Optionally, the methodology will be tested to search for real clandestine graves.

  16. Nuclear test ban verification

    International Nuclear Information System (INIS)

    This report describes verification and its rationale, the basic tasks of seismic verification, the physical basis for earthquake/explosion source discrimination and explosion yield determination, the technical problems pertaining to seismic monitoring of underground nuclear tests, the basic problem-solving strategy deployed by the forensic seismology resarch team at the University of Toronto, and the scientific significance of the team's research. The research carried out at the Univeristy of Toronto has two components: teleseismic verification using P wave recordings from the Yellowknife Seismic Array (YKA), and regional (close-in) verification using high-frequency Lg and Pn recordings from the Eastern Canada Telemetered Network. Major differences have been found in P was attenuation among the propagation paths connecting the YKA listening post with seven active nuclear explosion testing areas in the world. Significant revisions have been made to previously published P wave attenuation results, leading to more interpretable nuclear explosion source functions. (11 refs., 12 figs.)

  17. DOE/LLNL verification symposium on technologies for monitoring nuclear tests related to weapons proliferation

    International Nuclear Information System (INIS)

    The rapidly changing world situation has raised concerns regarding the proliferation of nuclear weapons and the ability to monitor a possible clandestine nuclear testing program. To address these issues, Lawrence Livermore National Laboratory's (LLNL) Treaty Verification Program sponsored a symposium funded by the US Department of Energy's (DOE) Office of Arms Control, Division of Systems and Technology. The DOE/LLNL Symposium on Technologies for Monitoring Nuclear Tests Related to Weapons Proliferation was held at the DOE's Nevada Operations Office in Las Vegas, May 6--7,1992. This volume is a collection of several papers presented at the symposium. Several experts in monitoring technology presented invited talks assessing the status of monitoring technology with emphasis on the deficient areas requiring more attention in the future. In addition, several speakers discussed proliferation monitoring technologies being developed by the DOE's weapons laboratories

  18. Ionospheric detection of the 25 May 2009 North Korean underground nuclear test

    Science.gov (United States)

    Park, Jihye; von Frese, Ralph R. B.; Grejner-Brzezinska, Dorota A.; Morton, Yu; Gaya-Pique, Luis R.

    2011-11-01

    The total electron content (TEC) measurements of the Global Navigation Satellite System (GNSS) revealed traveling ionospheric disturbances (TID) that locate North Korea's underground nuclear explosion (UNE) of 25 May 2009 to within about 3.5 km of its seismically determined epicenter. The random chance for this pattern of TIDs to register across the eleven GNSS stations is roughly 1 in 19 billion. Monte Carlo analysis of nearly 1,300 TIDs from a 7-station subset of the 11 GNSS stations supports the statistical strength of the array's signature. The UNE was also detected by seismic stations and possibly a local infrasound network of the International Monitoring System (IMS) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO), but no radionuclide evidence was found. Thus, global GNSS infrastructure enables mapping spatial and temporal variations of TEC that augment and complement other methods of detecting and locating clandestine UNEs.

  19. Proliferation Risks of Fusion Energy: Clandestine Production, Covert Production, and Breakout

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Goldston, A. Glaser, A.F. Ross

    2009-08-13

    Nuclear proliferation risks from fusion associated with access to weapon-usable material can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state begins production of fissile material without concealing the effort. In this paper we address each of these categories of risk from fusion. For each case, we find that the proliferation risk from fusion systems can be much lower than the equivalent risk from fission systems, if commercial fusion systems are designed to accommodate appropriate safeguards.

  20. The nuclear dissuasion without tests

    International Nuclear Information System (INIS)

    Since the signature of the french treaty against the nuclear tests (Tice) in 1995, the french engineers must used the simulation to warrant the performance and the safety of weapons. This paper recalls the historical aspects of the french nuclear tests and presents the technological and scientific resources to simulate a nuclear weapon operating. a special interest is given to the computer TERA. (A.L.B.)

  1. A comprehensive nuclear test ban

    International Nuclear Information System (INIS)

    The conclusion of a comprehensive nuclear test ban is of critical importance for the future of arms limitation and disarmament. As the 1980 report of the Secretary-General concluded, a comprehensive nuclear test ban is regarded as the first and most urgent step towards the cessation of the nuclear arms race and, in particular, of its qualitative aspects. It could serve as an important measure for the non-proliferation of nuclear weapons, both vertical and horizontal. It would have a major arms limitation impact in that it would make it difficult, if not impossible, to develop new designs of nuclear weapons and would also place constraints on the modification of existing weapon designs. The permanent cessation of all nuclear-weapon tests has long been sought by the world community and its achievement would be an event of great international significance

  2. Nuclear Test-Experimental Science

    International Nuclear Information System (INIS)

    Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program

  3. Introduction to nuclear test engineering

    International Nuclear Information System (INIS)

    The basic information in this report is from a vu-graph presentation prepared to acquaint new or prospective employees with the Nuclear Test Engineering Division (NTED). Additional information has been added here to enhance a reader's understanding when reviewing the material after hearing the presentation, or in lieu of attending a presentation

  4. The effects of nuclear tests

    International Nuclear Information System (INIS)

    The United States, the Sovjet Union, Britain, France and China have so far completed slightly over 2,000 nuclear tests. At first, the tests were mainly conducted in the atmosphere. The number of atmospheric tests done is slightly over 500. Explosions detonated in the atmosphere were dangerous to all those participating the tests -researchers, workers and military personnel - as well as to the inhabitants living near the test sites. The first hydrogen bomb test carried out by the United States on Bikini Atoll in 1954 caused radioactive fallout that contaminated the nearby atolls and made the crew of a Japanese fishing vessel fall ill. Soldiers participating in military drills conducted in connection with the tests were also exposed to the risks of the atmospheric explosions. Only a few atmospheric tests had direct health effects, but it is still being debated whether the resulting radiation doses affected the diseases that have surfaced later. The veil of secrecy kept up by all countries with nuclear weapons has hampered any investigations into the matter for decades. Nevertheless, in the last few years, some victims of the tests have been paid damages. (orig.) (1 fig.)

  5. Phase II: Field Detector Development For Undeclared/Declared Nuclear Testing For Treaty Verfiation Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kriz, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hunter, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Riley, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-02

    Radioactive xenon isotopes are a critical part of the Comprehensive Nuclear Test Ban Treaty (CTBT) for the detection or confirmation of nuclear weapons tests as well as on-site treaty verification monitoring. On-site monitoring is not currently conducted because there are no commercially available small/robust field detector devices to measure the radioactive xenon isotopes. Xenon is an ideal signature to detect clandestine nuclear events since they are difficult to contain and can diffuse and migrate through soils due to their inert nature. There are four key radioxenon isotopes used in monitoring: 135Xe (9 hour half-life), 133mXe (2 day half-life), 133Xe (5 day half-life) and 131mXe (12 day half-life) that decay through beta emission and gamma emission. Savannah River National Laboratory (SRNL) is a leader in the field of gas collections and has developed highly selective molecular sieves that allow for the collection of xenon gas directly from air. Phase I assessed the development of a small, robust beta-gamma coincidence counting system, that combines collection and in situ detection methodologies. Phase II of the project began development of the custom electronics enabling 2D beta-gamma coincidence analysis in a field portable system. This will be a significant advancement for field detection/quantification of short-lived xenon isotopes that would not survive transport time for laboratory analysis.

  6. Clandestineness and armed struggle: a look from the gender. the case of "Mery" in militancy clandestine Frente Patriótico Manuel Rodríguez

    OpenAIRE

    Javiera Libertad Robles Recabarren

    2013-01-01

    This paper focuses its concern on the participation of women in the struggle against the military dictatorship in Chile (1973 - 1988), with the aim of revealing my gender relations established within the clandestine militancy. To realize this, we turn to memoria suelta of a woman activist Frente Patriótico Manuel Rodríguez, who through the testimony of their experience exposes militant aspects of life from his position as woman, mother and clandestine, allowing unveil the place occupied by wo...

  7. Importance of testing in nuclear facilities

    International Nuclear Information System (INIS)

    In nuclear facilities systems and materials important for safety and reliability are frequently tested. This paper analyzes testing during design, building and operation of nuclear facilities. Then different aspects of test quality are examined: requirements, test programming, test quality, interfaces. Mainly new facilities, pilots or prototypes are concerned

  8. Nuclear science of Kazakhstan and former nuclear test site

    International Nuclear Information System (INIS)

    This abstract contains short historical notes on the genesis of Kazakhstan nuclear science, on Semipalatinsk former test site, information on main directions of investigations in Kazakhstan National Nuclear Centre, on activity of the centre on non-proliferation problems

  9. The Kosmo Club case: clandestine prostitution during the interwar period.

    Science.gov (United States)

    Settle, Louise

    2014-01-01

    During November 1933 the trial of three men accused of 'living off the earnings of prostitution' captivated the news reading public of Edinburgh. This article uses the detailed trial transcription and newspaper coverage of the Kosmo Club trial to examine the role that dance clubs played within a larger network of clandestine prostitution and the implications this had for the women who worked in these clubs as 'dance partners'. The case study focuses on a key moment in the history of prostitution, one that has not yet received sufficient historical attention, a moment when new technologies, such as the telephone and the motorcar, first began to dramatically alter the landscape of prostitution. Furthermore, the trial offers a rare glimpse of dance partners' experiences, both the dangers they faced and the many ways in which they attempted to resist those who sought to control and exploit them. PMID:25608372

  10. Ecological consequences of nuclear testing

    International Nuclear Information System (INIS)

    Many of the terrestrial disturbances on Amchitka Island resulting from nuclear testing were superimposed on scars remaining from military occupation. Construction, road improvement, and the Milrow and Cannikin nuclear detonations resulted in the loss or deterioration of about 420 ha (1040 acres) of terrestrial habitat, or less than 1.5% of the total area of Amchitka. A few streams and lakes were polluted by drilling effluents or human wastes; normal flushing action is expected to restore the quality of most of these freshwater habitats. Irreversible effects in freshwaters include the drainage of several ponds, gross channel alteration in a part of one stream, and the creation of a new lake which is deeper and which has a greater volume than any of the more than 2100 natural lakes on the southeast half of Amchitka. About 6 ha (15 acres) of intertidal bench was displaced to a level above the intertidal zone, and an undetermined amount of similar habitat was altered to some degree by lesser vertical displacement. No type of habitat on the island was destroyed, and localized habitat losses in the terrestrial, freshwater, and marine ecosystems are believed to have been too slight to have permanent effects on associated biotic populations

  11. Investigating effectiveness of clandestine advertisement and organizational strategy in brand management

    Directory of Open Access Journals (Sweden)

    M. R. Shojaei

    2014-12-01

    Full Text Available This investigation tries to examine correlation between clandestine advertisement and organizational strategy in brand management via available sources and by using a field study. In fact, it intends to raise the question “Are clandestine advertisement and organizational strategy effective in management of products brands?” This is an applied and descriptive-approaching study. The study chooses a sample of 171 regular customers who do their day-to-day banking business activities through an Iranian bank named Sepah bank in city of Tehran, Iran. Using structural equation modeling, the study confirms a positive and meaningful relationship between clandestine advertisement and organizational strategy in brand management.

  12. Importance of tests in nuclear facilities

    International Nuclear Information System (INIS)

    In nuclear facilities, safety related systems and equipments are subject, along their whole service-life, to numerous tests. This paper analyses the role of tests in the successive stages of design, construction, exploitation of a nuclear facility. It examines several aspects of test quality control: definition of needs, test planning, intrinsic quality of each test, control of interfaces (test are both the end and the starting point of many actions concerned by quality) and the application

  13. Investigating effectiveness of clandestine advertisement and organizational strategy in brand management

    OpenAIRE

    M. R. Shojaei; Sh. Sabaghi; N. Shirdel

    2014-01-01

    This investigation tries to examine correlation between clandestine advertisement and organizational strategy in brand management via available sources and by using a field study. In fact, it intends to raise the question “Are clandestine advertisement and organizational strategy effective in management of products brands?” This is an applied and descriptive-approaching study. The study chooses a sample of 171 regular customers who do their day-to-day banking business activities through an Ir...

  14. Political aspects of nuclear test effects at Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    The paper describes tense struggle of Kazakhstan people for closure of the Semipalatinsk Nuclear Test Site. It reveals major foreign policy aspects and nuclear test effects for both Kazakhstan and the world community. (author)

  15. Nuclear: Water-testing time?

    International Nuclear Information System (INIS)

    With Florida Power and Light Co reporting that five unnamed independent power producers specified nuclear powerplants in response to the utility's Request for Proposal for 800 MW (EW, January 1990, p 15), along with a report in McGraw-Hill's Nucleonics Week that Florida Public Service Commission (PSC) Chairman Michael Wilson told Westinghouse Electric Corp - developer of the AP-600 reactor - he did not have a knee-jerk reaction against nuclear power if it's done right, speculation increases that the state of Florida is one of the top locations in the US for the next nuclear order

  16. Ground test facility for nuclear testing of space reactor subsystems

    International Nuclear Information System (INIS)

    Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs

  17. The Comprehensive Nuclear Test Ban Treaty

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) is a cornerstone of the international regime on the non-proliferation of nuclear weapons and an essential foundation for the pursuit of nuclear disarmament. Its total ban of any nuclear weapon test explosion will constrain the development and qualitative improvement of nuclear weapons and end the development of advanced new types of these weapons. The Comprehensive Nuclear-Test-Ban Treaty was adopted by the United Nations General Assembly, and was opened for signature in New York on 24 September 1996. The Treaty will enter into force after it has been ratified by the 44 States listed in its Annex 2. These states possess nuclear power or research reactors. The Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO Preparatory Commission) is an international organization established by the States Signatories to the Treaty on 19 November 1996. It carries out the necessary preparations for the effective implementation of the Treaty, and prepares for the first session of the Conference of the States Parties to the Treaty. The Treaty has been signed and ratified by the Republic of Croatia and National Commission for the implementation of the Treaty has been established. Basic obligations of the Treaty, as specified in Article I, are: (1) Each State Party undertakes not to carry out any nuclear weapon test explosion or any other nuclear explosion, and to prohibit and prevent any such nuclear explosion at any place under its jurisdiction or control. (2) Each State Party undertakes, furthermore, to refrain from causing, encouraging, or in any way participating in the carrying out of any nuclear weapon test explosion or any other nuclear explosion.(author)

  18. Hitler's bomb: the secret story of Germans' attempts to get the nuclear weapon

    International Nuclear Information System (INIS)

    In this historical book, the author claims to have evidence concerning the development and testing of a possible 'nuclear weapon' by Nazi Germany in 1945. The 'weapon' in question is not alleged to be a standard nuclear weapon powered by nuclear fission, but something closer to either a radiological weapon (a so-called 'dirty bomb') or a hybrid-nuclear fusion weapon. Its new evidence is concerned primarily with the parts of the German nuclear energy project (an attempted clandestine scientific effort led by Germany to develop and produce atomic weapons during World War II) under Kurt Diebner, a German nuclear physicist who directed and administrated the project

  19. Comprehensive Nuclear Test-ban Treaty

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear Test-Ban Treaty was adopted by the General Assembly on 10 September 1996 (Res/50/245) and was open for signature by all states on 24 September 1996. It will enter into force 180 days after the date of deposit of the instruments of ratification by all states listed in Annex 2 to the Treaty. This document reproduces the text of the Treaty and the Protocol to the Comprehensive Nuclear Test-Ban Treaty Protocol to the Comprehensive Nuclear Test-Ban Treaty

  20. Soviet nuclear testing: The Republics say no

    International Nuclear Information System (INIS)

    Massive protests are taking place in Russia against nuclear weapons testing. Efforts have been mounted to stop all testing at Kazakhstan test site near the town of Semipalatinsk, site of the first nuclear detonation in 1949 and of more than 500 test conducted since. Boris Yeltsin proposed just after his election as president of the federation the elimination of testing grounds for nuclear and biological weapons on Russian territory. The central government in Moscow has announced that it is considering closing the Semipalatinsk site. Reaction has also been strong to testing at the Arctic island of Novaya Zemlya, and severe constraints, such as Arctic cold, frozen rocks, high winds, difficult access, and protests by Greenpeace activists and USSR's Nordic neighbors do not make this site attractive. The author feels that this movement in the USSR has set in motion a politically dynamic situation that makes for the best chance for a comprehensive test ban treaty yet witnessed

  1. Trustworthiness test of nuclear power station employees

    International Nuclear Information System (INIS)

    The trustworthiness test is an important part of securing nuclear facilities against internal offenders. For performing such a test the supervisory authority, which is the State's physical protection authority, contacts the security offices or authorities regarding persons who work inside the sensitive areas of nuclear power stations - areas containing nuclear material. The trustworthiness test covers the present activities of the employees and gives a prediction for the following five years; after this time the test must be repeated. The trustworthiness test is a prerequisite for a facility to obtain a licence for the use of nuclear material, to hire persons for work in the inner area of a nuclear facility or the hire persons for leading positions. In Germany the content and form of the test as well as the evaluation of the results are regulated in a guideline of the Federal Ministry for the Environment, Nature Conservation and Reactor Safety (BMU) (latest edition in June 1996). The test is performed by the licensing authority or the supervisory authority. the basis of the test is a declaration by the employee concerned, containing personal data and the agreement of the person to the use of the data files by the safety authorities. It the results of the test are positive, the person tested has the possibility to comment on differences or to explain certain facts. The paper presents details of the BMU guideline. (author)

  2. On the hydrostatic test for nuclear vessels

    International Nuclear Information System (INIS)

    A comparison of the pressure test requirements, namely specified values of pressure and temperature, for nuclear vessels designed and constructed according to the ASME Code and Spanish Rules is presented. Also the relationship of the design criteria and the pressure test requirements is indicated with a particular emphasis on the test temperature in order to avoid brittle behaviour of the materials. (author)

  3. Nuclear Fuel Test Rod Fabrication for Data Acquisition Test

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Chang-Young; Hong, Jin-Tae; Kim, Ka-Hye; Huh, Sung-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    A nuclear fuel test rod must be fabricated with precise welding and assembly technologies, and confirmed for their soundness. Recently, we have developed various kinds of processing systems such as an orbital TIG welding system, a fiber laser welding system, an automated drilling system and a helium leak analyzer, which are able to fabricate the nuclear fuel test rods and rigs, and keep inspection systems to confirm the soundness of the nuclear fuel test rods and rids. The orbital TIG welding system can be used with two kinds of welding methods. One can perform the round welding for end-caps of a nuclear fuel test rod by an orbital head mounted in a low-pressure chamber. The other can do spot welding for a pin-hole of a nuclear fuel test rod in a high-pressure chamber to fill up helium gas of high pressure. The fiber laser welding system can weld cylindrical and 3 axis samples such as parts of a nuclear fuel test rod and instrumentation sensors which is moved by an index chuck and a 3 axis (X, Y, Z) servo stage controlled by the CNC program. To measure the real-time temperature change at the center of the nuclear fuel during the irradiation test, a thermocouple should be instrumented at that position. Therefore, a hole needs to be made at the center of fuel pellet to instrument the thermocouple. An automated drilling system can drill a fine hole into a fuel pellet without changing tools or breaking the work-piece. The helium leak analyzer (ASM-380 model of DEIXEN Co.) can check the leak of the nuclear fuel test rod filled with helium gas. This paper describes not only the assembly and fabrication methods used by the process systems, but also the results of the data acquisition test for the nuclear fuel test rod. A nuclear fuel test rod for the data acquisition test was fabricated using the welding and assembling echnologies acquired from previous tests.

  4. Nuclear Fuel Test Rod Fabrication for Data Acquisition Test

    International Nuclear Information System (INIS)

    A nuclear fuel test rod must be fabricated with precise welding and assembly technologies, and confirmed for their soundness. Recently, we have developed various kinds of processing systems such as an orbital TIG welding system, a fiber laser welding system, an automated drilling system and a helium leak analyzer, which are able to fabricate the nuclear fuel test rods and rigs, and keep inspection systems to confirm the soundness of the nuclear fuel test rods and rids. The orbital TIG welding system can be used with two kinds of welding methods. One can perform the round welding for end-caps of a nuclear fuel test rod by an orbital head mounted in a low-pressure chamber. The other can do spot welding for a pin-hole of a nuclear fuel test rod in a high-pressure chamber to fill up helium gas of high pressure. The fiber laser welding system can weld cylindrical and 3 axis samples such as parts of a nuclear fuel test rod and instrumentation sensors which is moved by an index chuck and a 3 axis (X, Y, Z) servo stage controlled by the CNC program. To measure the real-time temperature change at the center of the nuclear fuel during the irradiation test, a thermocouple should be instrumented at that position. Therefore, a hole needs to be made at the center of fuel pellet to instrument the thermocouple. An automated drilling system can drill a fine hole into a fuel pellet without changing tools or breaking the work-piece. The helium leak analyzer (ASM-380 model of DEIXEN Co.) can check the leak of the nuclear fuel test rod filled with helium gas. This paper describes not only the assembly and fabrication methods used by the process systems, but also the results of the data acquisition test for the nuclear fuel test rod. A nuclear fuel test rod for the data acquisition test was fabricated using the welding and assembling echnologies acquired from previous tests

  5. Correlation testing for nuclear density functional theory

    International Nuclear Information System (INIS)

    Correlation testing provides a quick method of discriminating amongst potential terms to include in a nuclear mass formula or functional and is a necessary tool for further nuclear mass models; however a firm mathematical foundation of the method has not been previously set forth. Here, the necessary justification for correlation testing is developed and more detail of the motivation behind its use is given. Examples are provided to clarify the method analytically and for computational benchmarking. We provide a quantitative demonstration of the method's performance and short-comings, highlighting also potential issues a user may encounter. In concluding we suggest some possible future developments to improve the limitations of the method. (orig.)

  6. Non-Nuclear Testing of Space Nuclear Systems at NASA MSFC

    Science.gov (United States)

    Houts, Michael G.; Pearson, Boise J.; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky; Emrich, William J.; Garber, Anne; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.; Polzin, Kurt; Schoenfeld, Michael P.; Webster, Kenneth L.

    2010-01-01

    Highly realistic non-nuclear testing can be used to investigate and resolve potential issues with space nuclear power and propulsion systems. Non-nuclear testing is particularly useful for systems designed with fuels and materials operating within their demonstrated nuclear performance envelope. Non-nuclear testing allows thermal hydraulic, heat transfer, structural, integration, safety, operational, performance, and other potential issues to be investigated and resolved with a greater degree of flexibility and at reduced cost and schedule compared to nuclear testing. The primary limit of non-nuclear testing is that nuclear characteristics and potential nuclear issues cannot be directly investigated. However, non-nuclear testing can be used to augment the potential benefit from any nuclear testing that may be required for space nuclear system design and development. This paper describes previous and ongoing non-nuclear testing related to space nuclear systems at NASA's Marshall Space Flight Center (MSFC).

  7. Residues from nuclear testing at the test site Azgir

    International Nuclear Information System (INIS)

    The Azgir test site is situated in the western part of the Republic of Kazakhstan, about 180 km north of the Caspian Sea. The Azgir test site was used for conducting peaceful nuclear explosions from 1966 to 1979. 17 underground tests were carried out in 10 wells which created 9 special cavities in the salt with depths from 160 to 1500 m. The total volume of these cavities is about 1,000,000 cubic meter. Resulting from this activity, there is an environmental contamination that may have affected population living in the adjacent areas. The results of investigations of radiological conditions that were performed after the closing of the Azgir test site, and current activities of international and Kazakhstan's institutions for studying residues from nuclear tests are also discussed in this report. (author)

  8. Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan

    OpenAIRE

    Bernd Grosche; Tamara Zhunussova; Kazbek Apsalikov; Ausrele Kesminiene

    2015-01-01

    The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today’s radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose e...

  9. Nuclear cask testing films misleading and misused

    International Nuclear Information System (INIS)

    In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ''proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests

  10. Radiological criteria for underground nuclear tests

    International Nuclear Information System (INIS)

    The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry

  11. Aseismic design and testing of nuclear facilities

    International Nuclear Information System (INIS)

    Earthquake possibility is a main problem faced by certain countries concerning nuclear reactor siting and safety. To assist in finding solutions to earthquake problems, a Panel on Aseismic Design and Testing of Nuclear Facilities was held from 12 to 16 June 1967 in Tokyo. Paper presented in the Panel are condensed into recommendations that comprise this report. Topics discussed in this report are (i) basic philosophy of aseismic design (ii) site selection or evaluation (iii) aseismic design and (iv) future action including investigations and research problems. Tabs

  12. Nuclear weapon testing and the monkey business

    International Nuclear Information System (INIS)

    Reasons for India's total ban on the export of rhesus monkeys to U.S. have been explained. The major reason is that some of the animals were used in nuclear weapon related radiation experiments. This was a clear violation of a stricture in the agreement about supply of monkeys. The stricture prohibited the use of animals for research concerning military operations, including nuclear weapon testing. It is pleaded that a strict enforcement of strictures rather than a total ban on the export of monkeys would be better in the interest of advancement of knowledge in human medicine and disease control. (M.G.B.)

  13. Traditional nuclear physics as a test of nuclear exotics

    International Nuclear Information System (INIS)

    The review considers the testing of some exotic hypotheses about the properties of the nucleon in a nuclear medium in phenomena of traditional nuclear physics. The hypothesis of nucleon swelling proposed to explain the EMC effects is considered in detail. The consequences of this hypothesis for the charge densities and cross sections for scattering of fast electrons and protons by nuclei are analyzed. Also considered are the Nolen--Schiffer anomaly, the Coulomb sum rule for inelastic electron scattering, y scaling, and some other nuclear processes. It is shown that one can estimate the possible scale of nuclear exotics by analyzing many of these phenomena. Thus, examination of high-precision data on the elastic scattering of electrons with energy 500--700 MeV using density distributions calculated on the basis of the self-consistent theory of finite Fermi systems yields a restriction on the amount of nucleon swelling: α=δrN/rN approx-lt 10%. A similar analysis for protons with energy 0.8--1.0 GeV using Glauber theory gives α approx-lt 6%. An even more stringent restriction, α approx-lt 3%, follows from data on y scaling in 56Fe

  14. Nuclear Thermal Propulsion Ground Test History

    Science.gov (United States)

    Gerrish, Harold P.

    2014-01-01

    Nuclear Thermal Propulsion (NTP) was started in 1955 under the Atomic Energy Commission as project Rover and was assigned to Los Alamos National Laboratory. The Nevada Test Site was selected in 1956 and facility construction began in 1957. The KIWI-A was tested on July 1, 1959 for 5 minutes at 70MW. KIWI-A1 was tested on July 8, 1960 for 6 minutes at 85MW. KIWI-A3 was tested on October 10, 1960 for 5 minutes at 100MW. The National Aeronautics and Space Administration (NASA) was formed in 1958. On August 31, 1960 the AEC and NASA established the Space Nuclear Propulsion Office and named Harold Finger as Director. Immediately following the formation of SNPO, contracts were awarded for the Reactor In Flight Test (RIFT), master plan for the Nuclear Rocket Engine Development Station (NRDS), and the Nuclear Engine for Rocket Vehicle Application (NERVA). From December 7, 1961 to November 30, 1962, the KIWI-B1A, KIWI-B1B, and KIWI-B4A were tested at test cell A. The last two engines were only tested for several seconds before noticeable failure of the fuel elements. Harold Finger called a stop to any further hot fire testing until the problem was well understood. The KIWI-B4A cold flow test showed the problem to be related to fluid dynamics of hydrogen interstitial flow causing fuel element vibrations. President Kennedy visited the NTS one week after the KIWI-B4A failure and got to see the engine starting to be disassembled in the maintenance facility. The KIWI-B4D and KIWI-B4E were modified to not have the vibration problems and were tested in test cell C. The NERVA NRX program started testing in early 1964 with NRX-A1 cold flow test series (unfueled graphite core), NRX-A2 and NRX-A3 power test series up to 1122 MW for 13 minutes. In March 1966, the NRX-EST (Engine System Test) was the first breadboard using flight functional relationship and total operating time of 116 minutes. The NRX-EST demonstrated the feasibility of a hot bleed cycle. The NRX-A5 had multiple start

  15. Atmospheric methods for nuclear test monitoring

    International Nuclear Information System (INIS)

    The U.S. DOE sponsored research investigating atmospheric infrasound as a means of detecting both atmospheric and underground nuclear tests. Various detection schemes were examined and were found to be effective for different situations. It has been discovered that an enhanced sensitivity is realizable for the very lowest frequency disturbances by detecting the infrasound at the top of the atmosphere using ratio sound techniques. These techniques are compared to more traditional measurement schemes

  16. North Korea’s nuclear test

    OpenAIRE

    Radchenko, Sergey

    2009-01-01

    North Korea’s nuclear test serves several purposes. Its first purpose is to bolster the flagging legitimacy of the regime and, by drumming up war hysteria, achieve domestic mobilization in the face of mounting internal difficulties. Throughout North Korea’s turbulent history, the regime has periodically resorted to war hysteria, at times on even grander scale than what we have recently seen. North Korea’s Songun (army-first) policy requires periodic crises to maintain the myth of ...

  17. Biaxial dynamic testing of nuclear containment steel

    International Nuclear Information System (INIS)

    A test program has been initiated at the laboratories of the European Union Joint Research Centre of Ispra to investigate combined effects of high strain rates and biaxial stresses. The purpose is to assess the material behavior up to rupture in the special conditions which are produced during an explosion inside a nuclear metal containment. In the paper the main features of the campaign are discussed. (author). 19 refs., 4 figs

  18. Non-Nuclear Testing of Fission Technologies at NASA MSFC

    Science.gov (United States)

    Houts, Robert G.; Pearson, J. Boise; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky E.; Emrich, William J.; Garber, Anne E.; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.; Polzin, Kurt A.; Schoenfeld, Michael P.; Webster, Kenneth L.

    2011-01-01

    Highly realistic non-nuclear testing can be used to investigate and resolve potential issues with space nuclear power and propulsion systems. Non-nuclear testing is particularly useful for systems designed with fuels and materials operating within their demonstrated nuclear performance envelope. Non-nuclear testing also provides an excellent way for screening potential advanced fuels and materials prior to nuclear testing, and for investigating innovative geometries and operating regimes. Non-nuclear testing allows thermal hydraulic, heat transfer, structural, integration, safety, operational, performance, and other potential issues to be investigated and resolved with a greater degree of flexibility and at reduced cost and schedule compared to nuclear testing. The primary limit of non-nuclear testing is that nuclear characteristics and potential nuclear issues cannot be directly investigated. However, non-nuclear testing can be used to augment the potential benefit from any nuclear testing that may be required for space nuclear system design and development. This paper describes previous and ongoing non-nuclear testing related to space nuclear systems at NASA s Marshall Space Flight Center (MSFC).

  19. Environmental assessment report: Nuclear Test Technology Complex

    International Nuclear Information System (INIS)

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report

  20. New test of the nuclear statistical model

    International Nuclear Information System (INIS)

    High resolution proton resonance measurements provide a new test of the nuclear statistical model. For a sequence of levels with the same spin and parity the width correlation rho/sub W/ and the amplitude correlation rho/sub A/ are determined separately for the inelastic decay channels. The observed correlations average about 0.5 and are ascribed to direction reactions between the inelastic channels. For a multivariate Gausian distribution rho/sup 2//sub A//rho/sub W/=1. The present data provide the first opportunity to test this prediction directly

  1. Testing Iodine Filters for Nuclear Installations

    International Nuclear Information System (INIS)

    The removal efficiency of iodine filters for nuclear installations has been tested The test method in use includes laboratory tests of the adsorber material (under MCA conditions for temperature, relative humidity, pressure, loading, stay time and bed depth) and in-place tests at the site of the installation. For removal of methyl iodide under high relative humidity Kl-impregnated charcoal is widely used. Most of the data for charcoal removal efficiency available today result from experiments with tracer amounts of CH3131I mixed with CH3127I. Considering MCA conditions, the validity of those data should be confirmed for specific activities on charcoal 103 - 106 times higher. Experimental data are given for realistic loadings with CH3131I up to 10 Ci/g charcoal under 100% relative humidity. For standard laboratory adsorber tests a method is discussed for humidification and control of gas streams up to 100% relative humidity at elevated temperatures. The apparatus used is described. Experimental data are given for the removal efficiency and the adsorption of water in charcoal samples from long-time tests under 100% relative humidity. The overall test period was up to 98 h, simulating the phase of elevated pressure and, therefore, high iodine release from the reactor containment. The reproducibility of long-time tests under extremely high relative humidity is shown and discussed. A description of the hardware for in-place tests is included and results are given. (author)

  2. Field test of wireless sensor network in the nuclear environment

    International Nuclear Information System (INIS)

    Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

  3. Field test of wireless sensor network in the nuclear environment

    Energy Technology Data Exchange (ETDEWEB)

    Li, L., E-mail: lil@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Wang, Q.; Bari, A. [Univ. of Western Ontario, London, Ontario (Canada); Deng, C.; Chen, D. [Univ. of Electronic Science and Technology of China, Chengdu, Sichuan (China); Jiang, J. [Univ. of Western Ontario, London, Ontario (Canada); Alexander, Q.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2014-06-15

    Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

  4. Subsurface radionuclide investigation of a nuclear test

    Science.gov (United States)

    Mathews, M.; Hahn, K.; Thompson, J.; Gadeken, L.; Madigan, W.

    1994-08-01

    This paper reports on an environmental investigation into the vertical distribution of radionuclides from a nuclear test. Dalhart is the name of an underground nuclear test that was executed at the Nevada Test Site at a depth of 2100 ft on October 13, 1988. The test occurred below the static water level of 1667 ft and created multiple radioactive isotopes or fission products. These radioactive isotopes penetrated the surrounding formations and chimney region above the test and were retained there. A 19° 9- {7}/{8}-inch diameter slant hole was drilled to sample the geologic material in the chimney region above the Dalhart test for the purpose of assessing the distribution of radioactivity in and around the shot site. A 30-ft core recovered from a vertical depth of 1628 ft in the collapsed zone or chimney region and above the original static water level was found to be free of radionuclides. Drilling was completed to a vertical depth of 2156 ft with the present static water level at a vertical depth of 1644 ft. Gamma-ray spectroscopy log measurements, made within the drill pipe while drilling fluid was pumped through this pipe, indicate that radioactive material produced by the test was present from the vertical depth interval of 1746-2156 ft. Side-wall samples acquired from the vertical depth interval of 1721-2089 ft and analyzed in the field contained radionuclides such as 137Cs, 125Sb, 106Ru, plus the natural radioactive background of potassium, uranium, and thorium. These samples were sent to Los Alamos to determine the complete radionuclide content at each depth. These analyses were used with the gamma-ray spectroscopy logging data to determine the subsurface vertical radionuclide distribution at the Dalhart site.

  5. Subsurface radionuclide investigation of a nuclear test

    International Nuclear Information System (INIS)

    This paper reports on an environmental investigation into the vertical distribution of radionuclides from a nuclear test. Dalhart is the name of an underground nuclear test that was executed at the Nevada Test Site at a depth of 2100 ft on October 13, 1988. The test occurred below the static water level of 1667 ft and created multiple radioactive isotopes or fission products. These radioactive isotopes penetrated the surrounding formations and chimney region above the test and were retained there. A 19o 9-7/8-inch diameter slant hole was drilled to sample the geologic material in the chimney region above the Dalhart test for the purpose of assessing the distribution of radioactivity in and around the shot site. A 30-ft core recovered from a vertical depth of 1628 ft in the collapsed zone or chimney region and above the original static water level was found to be free of radionuclides. Drilling was completed to a vertical depth of 2156 ft with the present static water level at a vertical depth of 1644 ft. Gamma-ray spectroscopy log measurements, made within the drill pipe while drilling fluid was pumped through this pipe, indicate that radioactive material produced by the test was present from the vertical depth interval of 1746-2156 ft. Side-wall samples acquired from the vertical depth interval of 1721-2089 ft and analyzed in the field contained radionuclides such as 137Cs, 125Sb, 106Ru, plus the natural radioactive background of potassium, uranium, and thorium. These samples were sent to Los Alamos to determine the complete radionuclide content at each depth. These analyses were used with the gamma-ray spectroscopy logging data to determine the subsurface vertical radionuclide distribution at the Dalhart site

  6. Examination of the potential for diversion or clandestine dual use of a pebble-bed reactor to produce plutonium

    International Nuclear Information System (INIS)

    This paper explores the susceptibility of Pebble-Bed Reactors (PBRs) to be used overtly or covertly for the production of plutonium for nuclear weapons. The basic assumption made for the consideration of overt production is that a country would purchase a PBR with the ostensible motive of producing electric power; then, after the power plant was built, the country would divert the facility entirely to the production of weapons material. It is assumed that the country would then have to manufacture production pebbles from natural uranium. The basic assumption made for covert production is that the country would obtain and use a PBR for power production, but that it would clandestinely feed plutonium production pebbles through the reactor in such small numbers that the perturbation on power plant operation would be very difficult to detect. This paper shows the potential rate of plutonium production under such constraints. It is demonstrated that the PBR is a very poor choice for either form of proliferation-intent use. (author)

  7. Rehabilitation of nuclear test site at Maralinga

    International Nuclear Information System (INIS)

    A program to rehabilitate contaminated areas at the Maralinga Nuclear Test Range in South Australia is being undertaken by the Australian Department of Primary Industries and Energy (DPIE). A major part of the program is directed at reducing the risk presented by the contaminated debris buried at Taranaki, Maralinga's most heavily contaminated site. The rehabilitation program is using the insitu vitrification technology developed for the US Department of Energy. The program is now in its third phase, involving the construction of the full-scale treatment plant. This will be completed later this year. The fourth and last phase will involve the treatment of the Taranaki pits. This will commence in 1998. Tests carried out so far indicated that the normalized leach rates for all oxides in the vitrified product were less than 0.1g/m2. ills

  8. Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan

    Directory of Open Access Journals (Sweden)

    Bernd Grosche

    2015-05-01

    Full Text Available The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today’s radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose exposure and dosimetry, and evaluate new epidemiologic data and biological material collected from populations living in proximity to the test site. With time, new epidemiological data has been made available, and it is possible that these data may be linked to biological samples. Next to linking existing and newly available data to examine health effects, the existing dosimetry system needs to be expanded and further developed to include residential areas, which have not yet been taken into account. The aim of this paper is to provide an overview of previous studies evaluating the health effects of nuclear testing, including some information on dosimetry efforts, and pointing out directions for future epidemiologic studies.

  9. Experimental test of nuclear magnetization distribution and nuclear structure models

    International Nuclear Information System (INIS)

    Models exist that ascribe the nuclear magnetic fields to the presence of a single nucleon whose spin is not neutralized by pairing it up with that of another nucleon; other models assume that the generation of the magnetic field is shared among some or all nucleons throughout the nucleus. All models predict the same magnetic field external to the nucleus since this is an anchor provided by experiments. The models differ, however, in their predictions of the magnetic field arrangement within the nucleus for which no data exist. The only way to distinguish which model gives the correct description of the nucleus would be to use a probe inserted into the nucleus. The goal of our project was to develop exactly such a probe and to use it to measure fundamental nuclear quantities that have eluded experimental scrutiny. The need for accurately knowing such quantities extends far beyond nuclear physics and has ramifications in parity violation experiments on atomic traps and the testing of the standard model in elementary particle physics. Unlike scattering experiments that employ streams of free particles, our technique to probe the internal magnetic field distribution of the nucleus rests on using a single bound electron. Quantum mechanics shows that an electron in the innermost orbital surrounding the nucleus constantly dives into the nucleus and thus samples the fields that exist inside. This sampling of the nucleus usually results in only minute shifts in the electron s average orbital, which would be difficult to detect. By studying two particular energy states of the electron, we can, however, dramatically enhance the effects of the distribution of the magnetic fields in the nucleus. In fact about 2% of the energy difference between the two states, dubbed the hyperfine splitting, is determined by the effects related to the distribution of magnetic fields in the nucleus, A precise measurement of this energy difference (better than 0.01%) would then allow us to place

  10. Reload Startup Physics Tests for Tianwan Nuclear Power station

    International Nuclear Information System (INIS)

    This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)

  11. Xenon monitoring and the Comprehensive Nuclear-Test-Ban Treaty

    Energy Technology Data Exchange (ETDEWEB)

    Bowyer, Theodore W. [Nuclear Explosion Monitoring Program, Pacific Northwest National Laboratory, Richland, Washington 99352 (United States)

    2014-05-09

    How do you monitor (verify) a CTBT? It is a difficult challenge to monitor the entire world for nuclear tests, regardless of size. Nuclear tests 'normally' occur underground, above ground or underwater. Setting aside very small tests (let's limit our thinking to 1 kiloton or more), nuclear tests shake the ground, emit large amounts of radioactivity, and make loud noises if in the atmosphere (or hydroacoustic waves if underwater)

  12. Yesterday's, today's and tomorrow's nuclear tests of India and Pakistan

    International Nuclear Information System (INIS)

    This paper presents the historical aspects that led India and Pakistan to develop nuclear weapons and to perform nuclear weapon tests: weapons acquisition: today's military capacity, help from foreign countries; motivations: nuclear programs, geo-political aspects; results and potentialities; consequences for the non-proliferation systems and for the cut-off convention and test-ban treaties; and the geo-strategic consequences of todays's military nuclear capacity of India and Pakistan. (J.S.)

  13. Development of nuclear technologies and conversion of nuclear weapon testing system infrastructure in Kazakhstan

    International Nuclear Information System (INIS)

    The article gives a brief description of the work done by the National Nuclear Center of the Republic of Kazakhstan in development of nuclear technology and conversion of nuclear weapon testing infrastructure in Kazakhstan. Content and trends of works are as follows: 1. Peaceful use of all physical facilities, created earlier for nuclear tests in Kazakhstan; 2. Development of methods and technologies for safe nuclear reactors use; 3. Examination of different materials in field of great neutron flow for thermonuclear reactor's first wall development; 4. Liquidation of all wells, which were formed in the results of underground nuclear explosions in Degelen mountain massif of former Semipalatinsk test site; 5. Study of consequences of nuclear tests in West Kazakhstan (territory of Azgir test site and Karachaganak oil field); 6. Study of radiological situation on the Semipalatinsk test site and surrounding territories; 7. Search of ways for high-level radioactive wastes disposal; 8. Construction of safe nuclear power plants in Kazakhstan

  14. Some Qualitative Requirements for Testing of Nuclear Emergency Response Robots

    International Nuclear Information System (INIS)

    Korea Atomic Energy Research Institute (KAERI) is carrying out the project 'Development of Core Technology for Remote Response in Nuclear Emergency Situation', and as a part of the project, we are studying the reliability and performance requirements of nuclear emergency response robots. In this paper, we described some qualitative requirements for testing of nuclear emergency response robots which are different to general emergency response robots. We briefly introduced test requirements of general emergency response robots and described some qualitative aspects of test requirements for nuclear emergency response robots. When considering an immature field-robot technology and variety of nuclear emergency situations, it seems hard to establish quantitative test requirements of these robots at this time. However, based on studies of nuclear severe accidents and the experience of Fukushima NPP accident, we can expect some test requirements including quantitative ones for nuclear emergency response robots

  15. Some Qualitative Requirements for Testing of Nuclear Emergency Response Robots

    Energy Technology Data Exchange (ETDEWEB)

    Eom, Heungseop; Cho, Jai Wan; Choi, Youngsoo; Jeong, Kyungmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Korea Atomic Energy Research Institute (KAERI) is carrying out the project 'Development of Core Technology for Remote Response in Nuclear Emergency Situation', and as a part of the project, we are studying the reliability and performance requirements of nuclear emergency response robots. In this paper, we described some qualitative requirements for testing of nuclear emergency response robots which are different to general emergency response robots. We briefly introduced test requirements of general emergency response robots and described some qualitative aspects of test requirements for nuclear emergency response robots. When considering an immature field-robot technology and variety of nuclear emergency situations, it seems hard to establish quantitative test requirements of these robots at this time. However, based on studies of nuclear severe accidents and the experience of Fukushima NPP accident, we can expect some test requirements including quantitative ones for nuclear emergency response robots.

  16. Radioiodine prediction model for nuclear tests

    International Nuclear Information System (INIS)

    Over a 5-year period, 14 major experiments were conducted to investigate the air-forage-cow-milk system for transfer of radioiodine. The experiments included controlled releases using prepared aerosols, planned releases during Plowshare cratering tests, and releases due to accidental venting of underground nuclear tests. Two or more groups of dairy cows, three to six cows per group, were used in each experiment to study the effect on radioiodine transfer of such factors as: the mode of exposure, the type and state of forage fed, the type of aerosol, and variations in feeding practices. In each experiment, measurements were made of the total radioiodine intake and output in milk of the cows, the concentrations in forage and milk, the gaseous and particulate air concentrations, the open-field gamma exposure rate, and the deposition per unit area. The mean values of the experimental data are assembled in this report and are used to develop the parameters for a standard milk excretion pattern for dairy cows and to develop predictive equations for radioiodine. The resultant equations, for predicting the infinite dose to a 2-gram human thyroid caused by ingestion of 131I, are presented

  17. Current Status of Nuclear Fuel Irradiation Test at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Seong Woo; Park, Seung Jae; Shin, Yoon Taeg; Choo, Kee Nam; Cho, Man Soon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The in-pile testing of HANARO demand of not only the reactor core and structure material but also the nuclear fuel is recently increased to verify its irradiation performance, some fuel irradiation tests were planned and conducted using the irradiation test capsule in OR irradiation hole at HANARO. In this paper, the current status of irradiation test for the nuclear fuels at HANARO is reported. The current status of nuclear fuel irradiation test was reported. The irradiation test for plate, particle, pellet and metallic fuel for the development of research reactor, VHTR, LWR, SFR was planned and conducted at HANARO.

  18. Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

    International Nuclear Information System (INIS)

    This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines

  19. Nuclear fuel manufacturing. Testing nuclear materials and materials of nuclear interest

    International Nuclear Information System (INIS)

    Adopting CANDU system for nuclear energy production in Romania was argued by utilization of natural uranium, no isotopic enrichment being required for the fissile nuclide. Manufacturing the nuclear fuel, testing nuclear materials and materials for nuclear use, designing and realisation of the installations associated to the fabrication and testing were the main directions of activity of INR - Pitesti, from its inception. The report presents the main results in the fabrication of nuclear fuel and material testing. There are described the stages of fabrication of sintered powders of uranium dioxide starting from uranium nitrate solution. Efforts for refining uranium nitrate up to the required level of nuclear purity were eventually finalised by working out a technology of sintered uranium dioxide, a technology later on transferred to the pilot plant 'R' and then to the industrial Unit 'E'. In parallel, activities for processing of half-finished Zircaloy 4, for fabrication of sheathing components of uranium dioxide pellets and assembling of fuel clusters were developed. Over 100 experimental fuel elements were manufactured and pre-irradiation characterized in order to check the fabrication technologies as well as the computer codes for calculation of the CANDU type fuel behavior in normal and accident conditions. The irradiation testing of the fuel manufactured in INR was done in the NRU (Canada), MZFR (Germany), BR - 2 (Belgium) and TRIGA (Pitesti, Romania) reactors, while the post-irradiation examination was carried out in the hot loops of the INR reactor. In addition, other relating activities were developed as for instance: establishing technologies for re-entry in the fabrication flow of the UO2 sintered powders, of some recyclable materials and integral recovery of uranium from wastes; testing of the materials to be used in the UO2 sintering powders and identification of reagents and indigenous materials; implementation of the quality assurance systems; testing

  20. Nuclear Materials Management for the Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

  1. Analysis of North Korea's Nuclear Tests under Prospect Theory

    International Nuclear Information System (INIS)

    North Korea has chosen nuclear weapons as the means to protect its sovereignty. Despite international society's endeavors and sanctions to encourage North Korea to abandon its nuclear ambition, North Korea has repeatedly conducted nuclear testing. In this paper, the reason for North Korea's addiction to a nuclear arsenal is addressed within the framework of cognitive psychology. The prospect theory addresses an epistemological approach usually overlooked in rational choice theories. It provides useful implications why North Korea, being under a crisis situation has thrown out a stable choice but taken on a risky one such as nuclear testing. Under the viewpoint of prospect theory, nuclear tests by North Korea can be understood as follows: The first nuclear test in 2006 is seen as a trial to escape from loss areas such as financial sanctions and regime threats; the second test in 2009 was interpreted as a consequence of the strategy to recover losses by making a direct confrontation against the United States; and the third test in 2013 was understood as an attempt to strengthen internal solidarity after Kim Jong-eun inherited the dynasty, as well as to enhance bargaining power against the United States. Thus, it can be summarized that Pyongyang repeated its nuclear tests to escape from a negative domain and to settle into a positive one. In addition, in the future, North Korea may not be willing to readily give up its nuclear capabilities to ensure the survival of its own regime

  2. Nuclear test-experimental science annual report, Fiscal year 1990

    International Nuclear Information System (INIS)

    Fiscal year 1990 was another year of outstanding accomplishments for the Nuclear Test-Experimental Science (NTES) Program at Lawrence Livermore National Laboratory (LLNL). We continued to make progress to enhance the experimental science in the Weapons Program and to improve the operational efficiency and productivity of the Nuclear Test Program

  3. United States nuclear tests, July 1945 through September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

  4. Cancer in People Exposed to Nuclear Weapons Testing

    Science.gov (United States)

    ... Compensation Programs for People Exposed to Radiation as Part of Nuclear Weapons Testing Between 1945 and 1962, the United States ... involving about 200,000 people were conducted as part of many of these tests. ... several nuclear weapons plant sites were exposed to radiation and other ...

  5. Earth physicist describes US nuclear test monitoring system

    Science.gov (United States)

    1986-01-01

    The U. S. capabilities to monitor underground nuclear weapons tests in the USSR was examined. American methods used in monitoring the underground nuclear tests are enumerated. The U. S. technical means of monitoring Solviet nuclear weapons testing, and whether it is possible to conduct tests that could not be detected by these means are examined. The worldwide seismic station network in 55 countries available to the U. S. for seismic detection and measurement of underground nuclear explosions, and also the systems of seismic research observatories in 15 countries and seismic grouping stations in 12 countries are outlined including the advanced computerized data processing capabilities of these facilities. The level of capability of the U. S. seismic system for monitoring nuclear tests, other, nonseismic means of monitoring, such as hydroacoustic and recording of effects in the atmosphere, ionosphere, and the Earth's magnetic field, are discussed.

  6. The struggle of the veterans of the French nuclear tests

    International Nuclear Information System (INIS)

    The question debated in this article concerns the demand of compensation and recognition of the impact on their health of nuclear tests. The military personnel that worked during nuclear tests in French Polynesia and the Sahara sites, but also the inhabitants of the atolls of Moruroa and Fangataufa equally in French Polynesia. An observatory of the veterans health has been created in order to improve the medical management of military personnel and former military personnel. An association 'Moruroa e tatou' contains the Polynesian former workers of the Nuclear tests of the Pacific and the association A.V.E.N. contains the veterans of nuclear tests. numerous examples are detailed. The question is tackled too for the consequences on health of the British nuclear tests, in Australia, Christmas Islands, and New Zealand. (N.C.)

  7. Testing the nuclear will of Japan

    OpenAIRE

    Backer, David A.

    2007-01-01

    Increasing instability in the Northeast Asian region, decreasing faith in the U.S.-Japan security alliance, and the growing Chinese presence in the Northeast Asian region have caused Japanese politicians to revisit an issue that has been discussed three times in their history. The current issue is that, based on the above factors, Japan is once again considering whether or not the advantages of becoming a nuclear power outweigh the advantages of remaining a non-nuclear state. The purpose...

  8. Rover nuclear rocket engine program: Overview of rover engine tests

    Science.gov (United States)

    Finseth, J. L.

    1991-01-01

    The results of nuclear rocket development activities from the inception of the ROVER program in 1955 through the termination of activities on January 5, 1973 are summarized. This report discusses the nuclear reactor test configurations (non cold flow) along with the nuclear furnace demonstrated during this time frame. Included in the report are brief descriptions of the propulsion systems, test objectives, accomplishments, technical issues, and relevant test results for the various reactor tests. Additionally, this document is specifically aimed at reporting performance data and their relationship to fuel element development with little or no emphasis on other (important) items.

  9. DPRK nuclear test. Statement by IAEA Director General

    International Nuclear Information System (INIS)

    Full text: IAEA Director General Mohamed ElBaradei deeply regrets, and expresses serious concern, about the reported carrying-out of a nuclear test earlier today by the Democratic People's Republic of Korea (DPRK). This reported nuclear test threatens the nuclear non-proliferation regime and creates serious security challenges not only for the East Asian region but also for the international community. The breaking of a de-facto global moratorium on nuclear explosive testing that has been in place for nearly a decade and the addition of a new State with nuclear weapon capacity is a clear setback to international commitments to move towards nuclear disarmament, said the Director General. Dr. ElBaradei further reiterates the urgent need - more than any time before - for establishing a legally binding universal ban on nuclear testing through the early entry-into-force of the Comprehensive Nuclear-Test Ban Treaty. Dr. ElBaradei continues to believe in the importance of finding a negotiated solution to the current situation regarding the DPRK nuclear issue. The Director General believes that resumption of dialogue between all concerned parties is indispensable and urgent. (IAEA)

  10. Patterns of resistance and transgression in Eastern Indonesia: single women's practices of clandestine courtship and cohabitation.

    Science.gov (United States)

    Bennett, Linda Rae

    2005-03-01

    This paper explores how single women in the regional Indonesian city of Mataram express sexual desire in a social, cultural and political climate that idealizes the confinement of female sexuality within marriage. It is based on 21 months of ethnographic fieldwork conducted with single women, their families and health care providers. Success for young women in negotiating sexual desire is dependent upon their ability to maintain a faultless public reputation and mediate between their desires and those of men. Many single women find ways to pursue their desires by bending the rules of courtship conventions, performing sexual purity in public, while resisting from within the hegemonic sexual culture. However, women who visibly transgress dominant sexual ideals (and in doing so offend the status quo) are stigmatized and ostracized. Single women's practice of resistance and sexual transgression in premarital relationships are represented using the examples of pacaran backstreet (clandestine courtship) and cohabitation prior to marriage. PMID:16864191

  11. Recent irradiation tests for future nuclear system at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Man Soon; Choo, Kee Nam; Yang, Seong Woo; Park, Sang Jun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-05-15

    The capsule at HANARO is a device that evaluates the irradiation effects of nuclear materials and fuels, which can reproduce the environment of nuclear power plants and accelerate to reach to the end of life condition. As the integrity assessment and the extension of lifetime of nuclear power plants are recently considered as important issues in Korea, the requirements for irradiation test are gradually being increased. The capacity and capability irradiation tests at HANARO are becoming important because Korea strives to develop SFR (Sodium-cooled Fast Reactor) and VHTR (Very High Temperature Reactor) among the future nuclear system and to export the research reactors and to develop the fusion reactor technology.

  12. Recent irradiation tests for future nuclear system at HANARO

    International Nuclear Information System (INIS)

    The capsule at HANARO is a device that evaluates the irradiation effects of nuclear materials and fuels, which can reproduce the environment of nuclear power plants and accelerate to reach to the end of life condition. As the integrity assessment and the extension of lifetime of nuclear power plants are recently considered as important issues in Korea, the requirements for irradiation test are gradually being increased. The capacity and capability irradiation tests at HANARO are becoming important because Korea strives to develop SFR (Sodium-cooled Fast Reactor) and VHTR (Very High Temperature Reactor) among the future nuclear system and to export the research reactors and to develop the fusion reactor technology.

  13. Nuclear analyses of Indian LLCB test blanket system in ITER

    International Nuclear Information System (INIS)

    Heading towards the Nuclear Fusion Reactor Program, India is developing Lead Lithium Ceramic Breeder (LLCB) tritium breeding blanket for its future fusion Reactor. A mock-up of the LLCB blanket is proposed to be tested in ITER equatorial port no. 2, to ensure the overall performance of blanket in reactor relevant nuclear fusion environment. Nuclear analyses play an important role in LLCB Test Blanket System development. It is required for tritium breeding estimation, thermal-hydraulic design, coolants process design, radio-active waste management, equipments maintenance and replacement strategies and nuclear safety. To predict the nuclear behaviour of LLCB test blanket module in ITER, nuclear responses like tritium production, nuclear heating, neutron fluxes and radiation damages are estimated. As a part of ITER machine, LLCB TBS has to follow certain nuclear shielding requirements i.e. shutdown dose rates should not exceed the defined limits in ITER premises (inside bio-shield ∼100 μSv/hr after 12 days cooling and outside bio-shield ∼10 μSv/hr after 1 day cooling). Hence nuclear analyses are performed to assess and optimize the shielding capability of LLCB TBS inside and outside bio-shield. To state the radio-activity level of LLCB TBS components which support the rad-waste and safety assessment, nuclear activation analyses are executed. Nuclear analyses of LLCB TBS are performed using ITER recommended nuclear analyses codes (i.e. MCNP, EASY), nuclear cross section data libraries (i.e. FENDL 2.1, EAF) and neutronic model (ITER C-lite v.1). The paper describes comprehensive nuclear performance of LLCB TBS in ITER. (author)

  14. Testing quantum correlations with nuclear probes

    International Nuclear Information System (INIS)

    We investigated the feasibility of quantum-correlation measurements in nuclear physics experiments. In the first approach, we measured spin correlations of singlet-spin (1S0) proton pairs, which were generated in 1H(d,2He) and 12C(d,2He) nuclear charge-exchange reactions. The experiment was optimized for a clean preparation of the 2He singlet state and offered a 2π detection geometry for both protons in the exit channel. Our results confirm the effectiveness of the setup for these studies, despite limitations of a small data sample recorded during the feasibility studies

  15. Fate of 1-(1 Prime ,4 Prime -cyclohexadienyl)-2-methylaminopropane (CMP) in soil: Route-specific by-product in the clandestine manufacture of methamphetamine

    Energy Technology Data Exchange (ETDEWEB)

    Pal, Raktim [Centre for Environmental Risk Assessment and Remediation, University of South Australia, Mawson Lakes, Adelaide, South Australia, Australia-5095 and CRC for Contamination Assessment and Remediation of the Environment, University of South Australia (Australia); Megharaj, Mallavarapu, E-mail: Megharaj.Mallavarapu@unisa.edu.au [Centre for Environmental Risk Assessment and Remediation, University of South Australia, Mawson Lakes, Adelaide, South Australia, Australia-5095 and CRC for Contamination Assessment and Remediation of the Environment, University of South Australia (Australia); Kirkbride, K. Paul [Australian Federal Police Forensic and Data Centres, Canberra (Australia); Naidu, Ravi [Centre for Environmental Risk Assessment and Remediation, University of South Australia, Mawson Lakes, Adelaide, South Australia, Australia-5095 and CRC for Contamination Assessment and Remediation of the Environment, University of South Australia (Australia)

    2012-02-01

    We investigated the fate of 1-(1 Prime ,4 Prime -cyclohexadienyl)-2-methylaminopropane (CMP) in soil. CMP is the major route-specific byproduct in the clandestine manufacture of methamphetamine (MAP) by the use of excess alkali metal (e.g., lithium) in liquid ammonia, which is commonly referred to as the 'Nazi method'. This is one of the most common methods used in many countries for the illicit production of MAP. Knowledge on the fate of CMP in the terrestrial environment is essential to combat potential threats arising from illegal dumping of clandestine laboratory wastes. We report on the sorption-desorption, degradation, and metabolism patterns of CMP in three South Australian soils investigated in laboratory scale. CMP sorption in the test soils followed a Freundlich isotherm in the concentration range of 5 to 100 {mu}g mL{sup -1}. Degradation studies showed that CMP was fairly unstable in both non-sterile and sterile soils, with half-life values typically less than one week. The role of biotic and abiotic soil processes in the degradation of CMP also varied significantly between the different soils, and with the length of the incubation period. Interestingly, but not surprisingly, the results showed that the CMP was not actually degraded to any simpler compounds but transformed to more persistent MAP. Thus, the main concern with Nazi method is the potential hazard from MAP rather than CMP if wastes are disposed of into the environment. - Highlights: Black-Right-Pointing-Pointer This study investigated the fate of 1-(1 Prime ,4 Prime -cyclohexadienyl)-2-methylaminopropane (CMP) in soils. Black-Right-Pointing-Pointer CMP was fairly unstable in both non-sterile and sterile soils, with half-life values less than a week. Black-Right-Pointing-Pointer CMP transforms to more persistent methylamphetamine (MAP) in soils which is a major environmental concern.

  16. Fate of 1-(1′,4′-cyclohexadienyl)-2-methylaminopropane (CMP) in soil: Route-specific by-product in the clandestine manufacture of methamphetamine

    International Nuclear Information System (INIS)

    We investigated the fate of 1-(1′,4′-cyclohexadienyl)-2-methylaminopropane (CMP) in soil. CMP is the major route-specific byproduct in the clandestine manufacture of methamphetamine (MAP) by the use of excess alkali metal (e.g., lithium) in liquid ammonia, which is commonly referred to as the “Nazi method”. This is one of the most common methods used in many countries for the illicit production of MAP. Knowledge on the fate of CMP in the terrestrial environment is essential to combat potential threats arising from illegal dumping of clandestine laboratory wastes. We report on the sorption–desorption, degradation, and metabolism patterns of CMP in three South Australian soils investigated in laboratory scale. CMP sorption in the test soils followed a Freundlich isotherm in the concentration range of 5 to 100 μg mL−1. Degradation studies showed that CMP was fairly unstable in both non-sterile and sterile soils, with half-life values typically less than one week. The role of biotic and abiotic soil processes in the degradation of CMP also varied significantly between the different soils, and with the length of the incubation period. Interestingly, but not surprisingly, the results showed that the CMP was not actually degraded to any simpler compounds but transformed to more persistent MAP. Thus, the main concern with Nazi method is the potential hazard from MAP rather than CMP if wastes are disposed of into the environment. - Highlights: ► This study investigated the fate of 1-(1′,4′-cyclohexadienyl)-2-methylaminopropane (CMP) in soils. ► CMP was fairly unstable in both non-sterile and sterile soils, with half-life values less than a week. ► CMP transforms to more persistent methylamphetamine (MAP) in soils which is a major environmental concern.

  17. Nuclear weapons tests detectable worldwide by means of seismographic recording

    International Nuclear Information System (INIS)

    The site and intensity of nuclear weapons tests can be reliably determined by measurement and suitable interpretation of seismic waves. A seismic focus is up to 20 times larger than the destruction zone of a comparably strong explosion, so that a seismic event will last longer by one order of magnitude than an explosion. Nuclear weapons tests induce much more high-frequency vibrations than a seismic event, and a seismic event normally proceeds in a series of subsequent shocks. Diaphragms applied in the range 10 to 30 Hz considerably improve the signal-to-noise ratio of systems for the detection of nuclear weapons tests. (orig./DG)

  18. Semipalatinsk nuclear test site: History of building and function

    International Nuclear Information System (INIS)

    A vast materials on history of Semipalatinsk nuclear test site creation and it building and function are presented. Authors with big reliability report one page of Kazakhstan's history. In steppe on naked place thousands of soldiers and officers, construct and military specialists have built the nuclear site on which during 40 years were conducting nuclear tests . Prolonged chronic radiation on population living near by site results to tragedy which is confessed by General Assembly of United Nations. In the book aspects of test site conversion and rehabilitation of injured population are considered. The book consists of introduction, three chapters and conclusion. The book is intended to wide circle of readers. (author)

  19. Fabrication Process of a Nuclear Fuel Test Rig in HANARO

    International Nuclear Information System (INIS)

    To evaluate the performance of newly developed PWR nuclear fuels, an adequate test rig installed in a pressure vessel of IPS, as a part of FTL (Fuel Test Loop) should be fabricated to meet the irradiation purposes. Generally, a nuclear fuel test rig is designed to measure the central temperature of a nuclear fuel pellet and the internal pressure of a fuel rod during an irradiation test. In special cases, it is also designed to measure the swelling or elongation of the fuel rod. The fabrication process of a nuclear fuel test rig that includes a detachable fuel rod assembly has been introduced in this study. Key techniques to fabricate a nuclear fuel test rig have been developed and used in fabricating a test rig mockup. Therefore, to fabricate a new test rig, the tooling of the components and making sub-assemblies that do not include nuclear fuels are out sourced, and the key assembly and sealing processes are carried out in the controlled area using the developed techniques

  20. Fabrication Process of a Nuclear Fuel Test Rig in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jintae; Joung, Chang-Young; Ahn, Sung-Ho; Heo, Sung-Ho; Kim, Jin-Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    To evaluate the performance of newly developed PWR nuclear fuels, an adequate test rig installed in a pressure vessel of IPS, as a part of FTL (Fuel Test Loop) should be fabricated to meet the irradiation purposes. Generally, a nuclear fuel test rig is designed to measure the central temperature of a nuclear fuel pellet and the internal pressure of a fuel rod during an irradiation test. In special cases, it is also designed to measure the swelling or elongation of the fuel rod. The fabrication process of a nuclear fuel test rig that includes a detachable fuel rod assembly has been introduced in this study. Key techniques to fabricate a nuclear fuel test rig have been developed and used in fabricating a test rig mockup. Therefore, to fabricate a new test rig, the tooling of the components and making sub-assemblies that do not include nuclear fuels are out sourced, and the key assembly and sealing processes are carried out in the controlled area using the developed techniques.

  1. Nuclear Weapons Tests and Environmental Consequences: A Global Perspective

    OpenAIRE

    Prăvălie, Remus

    2014-01-01

    The beginning of the atomic age marked the outset of nuclear weapons testing, which is responsible for the radioactive contamination of a large number of sites worldwide. The paper aims to analyze nuclear weapons tests conducted in the second half of the twentieth century, highlighting the impact of radioactive pollution on the atmospheric, aquatic, and underground environments. Special attention was given to the concentration of main radioactive isotopes which were released, such as 14C, 137...

  2. Detailed Burnup Calculations for Testing Nuclear Data

    Science.gov (United States)

    Leszczynski, F.

    2005-05-01

    A general method (MCQ) has been developed by introducing a microscopic burnup scheme that uses the Monte Carlo calculated fluxes and microscopic reaction rates of a complex system and a depletion code for burnup calculations as a basis for solving nuclide material balance equations for each spatial region in which the system is divided. Continuous energy-dependent cross-section libraries and full 3D geometry of the system can be input for the calculations. The resulting predictions for the system at successive burnup time steps are thus based on a calculation route where both geometry and cross sections are accurately represented, without geometry simplifications and with continuous energy data, providing an independent approach for benchmarking other methods and nuclear data of actinides, fission products, and other burnable absorbers. The main advantage of this method over the classical deterministic methods currently used is that the MCQ System is a direct 3D method without the limitations and errors introduced on the homogenization of geometry and condensation of energy of deterministic methods. The Monte Carlo and burnup codes adopted until now are the widely used MCNP and ORIGEN codes, but other codes can be used also. For using this method, there is need of a well-known set of nuclear data for isotopes involved in burnup chains, including burnable poisons, fission products, and actinides. For fixing the data to be included in this set, a study of the present status of nuclear data is performed, as part of the development of the MCQ method. This study begins with a review of the available cross-section data of isotopes involved in burnup chains for power and research nuclear reactors. The main data needs for burnup calculations are neutron cross sections, decay constants, branching ratios, fission energy, and yields. The present work includes results of selected experimental benchmarks and conclusions about the sensitivity of different sets of cross

  3. On the population dose around the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Since 1949 the Semipalatinsk Nuclear Test Site (NTS) was extensively used by the former Soviet government as a testing range for atomic weapons. Atmospheric and underground tests were finally stopped in 1962 and 1989, respectively. The Ministry of the Russian Federation of Atomic Energy officially counts a total of 456 tests, including 116 atmospheric tests. The total yield of the nuclear explosions carried out was 6.3 Megatons equivalent with 6.7 PetaBq of 137Cs and 3.7 PetaBq of 90Sr being released into the athmosphere. Some of the athmospheric radioactive tests shielded plumes, which extended far beyond the outer borders of the NTS. Already the first Soviet atomic bomb test on August 29, 1949 due to unfavourable meteorological conditions affected the villages of Dolon and Moistik. Since 1995 joint investigations performed by the Research Centre Julich in cooperation with the Kazakh National Nuclear Centre in the region of the former nuclear test site near Semipalatinsk besides environmental measurents also involve the assessment of the current dose of the population at and around the test site in addition to the important retrospective determination of the dose of persons affected by the atmospheric tests

  4. Los Alamos studies of the Nevada test site facilities for the testing of nuclear rockets

    Science.gov (United States)

    Hynes, Michael V.

    1993-01-01

    The topics are presented in viewgraph form and include the following: Nevada test site geographic location; location of NRDA facilities, area 25; assessment program plan; program goal, scope, and process -- the New Nuclear Rocket Program; nuclear rocket engine test facilities; EMAD Facility; summary of final assessment results; ETS-1 Facility; and facilities cost summary.

  5. Nuclebras' installations for performance tests of nuclear power plants components

    International Nuclear Information System (INIS)

    The reasons for Nuclebras' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufactures, giving to them the means for performing functional tests of industrial products, are presented. A brief description of facilities under construction: the components Test Loop and Facility for Testing N.P.P. components under Accident conditions, and other already in operation, as well as its objectives and main technical characteristics. Some test results had already obtained are also presented. (Author)

  6. NUCLEBRAS' installations for tests of nuclear power plants components

    International Nuclear Information System (INIS)

    The reasons for NUCLEBRAS' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufacturers, giving to them the means for performing functional tests of industrial products, are presented. A brief description of the facilities under construction: the Components Test Loop and the Facility for Testing N.P.P. Components under Accident Conditions, and of other already in operation, is given, as well as its objectives and main technical characteristics. Some test results already obtained are also presented. (Author)

  7. The startup physics tests of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    The first startup physics tests of Qinshan Nuclear Power Company's 300 MW PWR are presented. These include the first initial criticality and low power physics tests. Testing items include critical boron concentration, control rod worth, boron worth, power distribution, temperature coefficient of moderator, minimum shutdown boron concentration, rod cluster shoot-out worth, etc. The results of tests verified that the basic requirements for the design and safety of the core have been satisfied

  8. Performance tests for integral reactor nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Dong-Seong; Yim, Jeong-Sik; Lee, Chong-Tak; Kim, Han-Soo; Koo, Yang-Hyun; Lee, Byung-Ho; Cheon, Jin-Sik; Oh, Je-Yong

    2006-02-15

    An integral type reactor SMART plans to utilize metallic Zr-U fuel which is Zr-based alloy with 34{approx}38 wt% U. In order to verify the technologies for the design and manufacturing of the fuel and get a license, performance tests were carried out. Experimental Fuel Assembly (EFA) manufactured in KAERI is being successfully irradiated in the MIR reactor of RIAR from September 4 2004, and it has achieved burnup of 0.21 g/cc as of January 25 2006. Thermal properties of irradiated Zr-U fuel were measured. Up to the phase transformation temperature, thermal diffusivity increased linearly in proportion to temperature. However its dependence on the burnup was not significant. RIA tests with 4 unirradiated Zr-U fuel rods were performed in Kurchatov Institute to establish a safety criterion. In the case of the un-irradiated Zr-U fuel, the energy deposition during the control rod ejection accident should be less than 172 cal/g to prevent the failure accompanying fuel fragmentation and dispersal. Finally the irradiation tests of fuel rods have been performed at HANARO. The HITE-2 test was successfully completed up to a burnup of 0.31 g/cc. The HITE-3 test began in February 2004 and will be continued up to a target burnup of 0.6 g/cc.

  9. Performance tests for integral reactor nuclear fuel

    International Nuclear Information System (INIS)

    An integral type reactor SMART plans to utilize metallic Zr-U fuel which is Zr-based alloy with 34∼38 wt% U. In order to verify the technologies for the design and manufacturing of the fuel and get a license, performance tests were carried out. Experimental Fuel Assembly (EFA) manufactured in KAERI is being successfully irradiated in the MIR reactor of RIAR from September 4 2004, and it has achieved burnup of 0.21 g/cc as of January 25 2006. Thermal properties of irradiated Zr-U fuel were measured. Up to the phase transformation temperature, thermal diffusivity increased linearly in proportion to temperature. However its dependence on the burnup was not significant. RIA tests with 4 unirradiated Zr-U fuel rods were performed in Kurchatov Institute to establish a safety criterion. In the case of the un-irradiated Zr-U fuel, the energy deposition during the control rod ejection accident should be less than 172 cal/g to prevent the failure accompanying fuel fragmentation and dispersal. Finally the irradiation tests of fuel rods have been performed at HANARO. The HITE-2 test was successfully completed up to a burnup of 0.31 g/cc. The HITE-3 test began in February 2004 and will be continued up to a target burnup of 0.6 g/cc

  10. Seismic qualification tests of nuclear service pressure relief valves

    International Nuclear Information System (INIS)

    This paper reports on the pressure relief valves which provide an overpressure protection of vessels and piping in the nuclear power plant. A seismic qualification of these valves is essential to ensure their structural integrity and operability under earthquake and other dynamic conditions. Four spring loaded pressure relief valves were qualified by dynamic testing in response to a need for an overseas nuclear power plant construction. The test valves were actual production valves in 3/4 to 3 inch sizes and weighed approximately 11 to 110 lb. Each valve was subjected to triaxial random multifrequency testing (RMF), resonance search testing, sine beat testing and impact resonance search testing. Very briefly, the dynamic test conditions enveloped the specified required response spectra (RRS) and required input motion (RIM) vibratory conditions. Each valve input motion (RIM) vibratory conditions. Each valve was also tested to determine valve action, opening pressure and lift characteristics prior to, during, and after various dynamic tests. The valve leakage was also checked except during the dynamic testing. The test results showed very satisfactory operability of all four valves before, during and after the dynamic tests. These and other geometrically/functionally similar valves have also met the seismic qualification requirements of several other domestic and overseas nuclear power plants

  11. The impact of the multilateral approach to the nuclear fuel cycle in Malaysia's nuclear fuel cycle policy

    International Nuclear Information System (INIS)

    Since the Pakistan-India nuclear weapon race, the North Korean nuclear test and the September 11 attack revealed Abdul Qadeer Khan's clandestine nuclear black market and the fear that Iran's nuclear program may be used for nuclear weapon development, scrutiny of activities related to nuclear technologies, especially technology transfer has become more stringent. The nuclear supplier group has initiated a multilateral nuclear fuel cycle regime with the purpose of guaranteeing nuclear fuel supply and at the same time preventing the spread of nuclear proliferation. Malaysia wants to develop a programme for the peaceful use of nuclear energy and it needs to accommodate itself to this policy. When considering developing a nuclear fuel cycle policy, the key elements that Malaysia needs to consider are the extent of the fuel cycle technologies that it intends to acquire and the costs (financial and political) of acquiring them. Therefore, this paper will examine how the multilateral approach to the nuclear fuel cycle may influence Malaysia's nuclear fuel cycle policy, without jeopardising the country's rights and sovereignty as stipulated under the NPT. (authors)

  12. Proving test on the reliability for nuclear valves

    International Nuclear Information System (INIS)

    Since valves are the most common components, they could be the most frequent causes of troubles in nuclear power plants. This proving test, therefore, has an important meaning to examine and verify the reliability of various valves under simulating conditions of abnormal and transient operations of the nuclear power plant. The test was performed mainly for the various types and pressure ratings of valves which were used in the primary and secondary systems in BWR and PWR nuclear power plants and which had major operating or safety related functions in those nuclear power plants. The results of the proving test, confirmed for more than four years, showed relatively favourable performance of the tested valves. It is concluded that performances of valves including operability, seat sealing and structural integrity were proved under the thermal cycling, vibration and pipe reaction load conditions. Operating functions during and after accident such as loss of coolant accident were satisfactory. From these results, it was considered that the purpose of this proving test was satisfactorily fulfilled. Several data accumulated by the test would be useful to get better reliability if it was evaluated with the actually experienced data of valves in the nuclear power plants. (Nogami, K.)

  13. Verifying seismic design of nuclear reactors by testing. Volume 1: test plan

    International Nuclear Information System (INIS)

    This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program

  14. OFF-SITE MONITORING FOR THE MIGHTY OAK NUCLEAR TEST

    Science.gov (United States)

    After a nuclear explosives test, code name Mighty Oak, the tunnel leading to the test point became contaminated with radioactive debris. To re-enter and recover valuable equipment and data, the DOE purged the tunnel air using particulate and charcoal filters to minimize discharge...

  15. Task force for integral test of High Energy nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    According to completion of the JENDL-High Energy file for neutron nuclear cross sections up to 50 MeV, a task force for integral test of high energy nuclear data was organized to discuss a guide line for integral test activities. A status of existing differential and integral experiments and how to perform such a test were discussed in the task force. Here the purpose and outline of the task force is explained with some future problems raised in discussion among the task member. (author)

  16. Nuclear Test-Experimental Science: Annual report, fiscal year 1988

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

    1988-01-01

    Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

  17. The Nuclear Non-Proliferation Treaty and the Comprehensive Nuclear-Test-Ban Treaty, the relationship

    Energy Technology Data Exchange (ETDEWEB)

    Graham, Thomas Jr. [7609 Glenbrook Rd., Bethesda, MD 20814 (United States)

    2014-05-09

    The Nuclear Non-Proliferation Treaty (NPT) is the most important international security arrangement that we have that is protecting the world community and this has been true for many years. But it did not happen by accident, it is a strategic bargain in which 184 states gave up the right forever to acquire the most powerful weapon ever created in exchange for a commitment from the five states allowed to keep nuclear weapons under the NPT (U.S., U.K., Russia, France and China), to share peaceful nuclear technology and to engage in disarmament negotiations aimed at the ultimate elimination of their nuclear stockpiles. The most important part of this is the comprehensive nuclear test ban (CTBT); the thinking by the 184 NPT non-nuclear weapon states was and is that they understand that the elimination of nuclear weapon stockpiles is a long way off, but at least the NPT nuclear weapon states could stop testing the weapons. The CTBT has been ratified by 161 states but by its terms it can only come into force if 44 nuclear potential states ratify; 36 have of the 44 have ratified it, the remaining eight include the United States and seven others, most of whom are in effect waiting for the United States. No state has tested a nuclear weapon-except for complete outlier North Korea-in 15 years. There appears to be no chance that the U.S. Senate will approve the CTBT for ratification in the foreseeable future, but the NPT may not survive without it. Perhaps it is time to consider an interim measure, for the UN Security Council to declare that any future nuclear weapon test any time, anywhere is a 'threat to peace and security', in effect a violation of international law, which in today's world it clearly would be.

  18. Space Nuclear Thermal Propulsion Nuclear Element Tests at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Nuclear Element Tests (NET) are being performed as part of the U.S. Air Force Space Nuclear Thermal Propulsion (SNTP) Program to evaluate high performance fuel elements intended for use in future nuclear propulsion systems. The NET experiments are to be performed at the Sandia National Laboratories (SNL's) Annular Core Research Reactor (ACRR). Objectives of these experiments are to provide engineering validation and demonstration of critical-fuel-element-related technologies and an experimental data base to support analytical design methods for the SNTP Program. Currently, hardware for the first two fueled NET experiments has been fabricated, and cold flow tests have been accomplished with a representative set of hardware to assure the experimental capability to achieve test objectives in-reactor. Assembly of the first NET experiment to test a representative nuclear fuel element is in progress, and planned operational sequences have been defined

  19. Importance of the quality control tests in nuclear medicine

    International Nuclear Information System (INIS)

    Full text: The acceptance of nuclear energy and its application by some part of the population are associated with the benefits brought by those activities and the guarantee that the incorporation of this technology will be strictly done according to the currently security norms. This project aims at presenting the Nuclear Medicine tests of control of quality models to assist the National Commission of Nuclear Energy Program of Regulatory Inspection (CNEN). The main aspects related with the radiological protection are discussed along the project and it is presented models that assist the Nuclear Medicine Service, in the matter of Radioprotection paying attention to the requirements of the Regulatory Inspection of CNEN. The fulfilment of such models shows, clearly, that they are fundamental for the radioprotection safety in the Nuclear Medicine Services. (author)

  20. Survey of hazardous materials used in nuclear testing

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, E.A.; Fabryka-Martin, J.

    1991-02-01

    The use of hazardous'' materials in routine underground nuclear tests at the Nevada Test Site has been reviewed. In addition the inventory of test yields, originally reported in 1976 has been updated. A trail down-hole inventory'' has been conducted for a selected test. The inorganic hazardous materials introduced during testing (with the exception of lead and the fissionable materials) produce an incremental change in the quantity of such materials already present in the geologic media surrounding the test points. 1 ref., 3 tabs.

  1. Devices (manipulators) particularly for ultrasonic tests in nuclear power stations

    International Nuclear Information System (INIS)

    The manipulator devices for internal and external tests described in this article, were used successfully in the basic and repeat tests for nearly all West German, Swiss and Austrian nuclear power stations. For older reactors or for reactors originating from abroad one did not take sufficient account of the required accessibility to the test location in the configuration of the reactor pressure vessel, which led to complicated special manipulation devices. The handling of which at site requires a great deal of time. The more modern types of reactors are laid out so as to be easier to test and make a better manipulation test system and better test results possible. (orig./RW)

  2. Nuclear Test Ban: Converting Political Visions to Reality

    Science.gov (United States)

    Suárez, Gerardo

    2010-05-01

    Negotiations to ban or at least restrict nuclear explosions began not long after the first test was conducted, in the Alamogordo desert of New Mexico on 16 July 1945. In August of that same year, the world witnessed the devastation of the Japanese cities of Hiroshima and Nagasaki and the horrifically destructive power that these weapons are capable of unleashing. Almost 50 years later, the long and tortuous road to negotiating a treaty that comprehensively bans nuclear explosions, whether for alleged peaceful purposes or for weapons development, culminated on 24 September 1996 when the Comprehensive Nuclear-Test-Ban Treaty (CTBT) was opened for signature. In a surge of enthusiasm, that first day the treaty was signed by more than 70 nations, including the five acknowledged nuclear powers. Addressing the United Nations General Assembly, U.S. President Bill Clinton described the CTBT as “the longest-sought, hardest-fought prize in the history of arms control.”

  3. Radioactive fallout in the southern hemisphere from nuclear weapons tests

    International Nuclear Information System (INIS)

    Fallout in the southern hemisphere, and its origins in the national programs of atmospheric nuclear weapons testing in both hemispheres, are reviewed. Of the 390 nuclear tests conducted in the atmosphere to date, 53 were carried out in the southern hemisphere and it is the second phase of these, between 1966 and 1974, that is seen to have been responsible for the main fallout of short-lived fission products in the southern hemisphere. In contrast to this, the programs of atmospheric nuclear testing in the northern hemisphere up to 1962 are shown to have been the main source of long-lived fission products in fallout in the southern hemisphere. The course followed by this contamination through the environment of the southern hemisphere is traced for the national programs of nuclear testing after 1962 taken separately (France, China) and for the earlier national programs taken together (U.S.S.R., U.S.A. and U.K.). The impact on populations in the southern hemisphere of fallout from atmospheric nuclear weapons tests to date is assessed

  4. A new role of proficiency testing in nuclear analytical work

    DEFF Research Database (Denmark)

    Heydorn, Kaj

    2008-01-01

    The most recent definition of measurement result requires a statement of uncertainty whenever results obtained by nuclear or other quantitative methods of analysis are reported. Proficiency testing (PT) therefore must include the ability of laboratories to present not only unbiased quantity values...... laboratory intercomparison of uranium isotopic ratios with very low reported uncertainties. In the paper this example is used to present the situation in the nuclear field....

  5. Nuclear commissioning of the NRU blowdown test facility

    International Nuclear Information System (INIS)

    The Blowdown Test Facility in the NRU reactor will be used to conduct all-effects experiments under postulated Loss-of-Coolant Accident and Severe Fuel Damage conditions. Experiments conducted in the BTF will provide information on the release, transport and deposition of fission products, and the thermal and mechanical behaviour of nuclear fuel under these conditions. This paper describes results from the nuclear commissioning experiment for the BTF. (2 refs., 4 figs.)

  6. On site inspection for nuclear test ban verirication

    OpenAIRE

    P. D. Marschall

    1994-01-01

    The problem of verifying compliance with a nuclear test ban treaty is mainly a technical one. However the problem of detecting, locating and identifying nuclear explosions has, since the late 1950s, been intimately involved with the political problems associated with negotiating a treaty. In fact there are few other areas in which policy, diplomacy and science have been so interwoven. This paper attempts to illustrate how technology can. be applied to solve some of the political problems whic...

  7. Special tests of building structures of Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Two demanding safety tests for leaks are described applied to building structures of the Dukovany nuclear power plant. A hydrostatic leak test was conducted of tanks permanently or temporarily flooded, and an integral leak test was performed of the power plant sealed space. The objective was to show that the structures are leakproof in case of a hypothetical accident of the production unit. The hydrostatic leak test was performed by flooding the central part with 500 m3 of demineralized water. For the integral leak test the sealed space was pressurized with air to a value of 144 kPa. Defects inside the sealed space were continuously detected and removed. The lose of air in 24 hours was calculated. It is recommended that the experience gained should be used to work out standard requirements on leak tests of building structures of nuclear power plants. (Pu)

  8. Crash testing of nuclear fuel shipping containers

    International Nuclear Information System (INIS)

    In an attempt to understand the dynamics of extra severe transportation accidents and to evaluate state-of-the-art computational techniques for predicting the dynamic response of shipping casks involved in vehicular system crashes, the Environmental Control Technology Division of ERDA undertook a program with Sandia to investigate these areas. The program encompasses the following distinct major efforts. The first of these utilizes computational methods for predicting the effects of the accident environment and, subsequently, to calculate the damage incurred by a container as the result of such an accident. The second phase involves the testing of 1/8-scale models of transportation systems. Through the use of instrumentation and high-speed motion photography the accident environments and physical damage mechanisms are studied in detail. After correlating the results of these first two phases, a full scale event involving representative hardware is conducted. To date two of the three selected test scenarios have been completed. Results of the program to this point indicate that both computational techniques and scale modeling are viable engineering approaches to studying accident environments and physical damage to shipping casks

  9. Periodic testing of safety valves of nuclear facilities

    International Nuclear Information System (INIS)

    The report is concerned with the periodic performance testing of the pressure relief devices, i.e. safety and relief valves, used in nuclear power plants. The factors affecting the operation of safety and relief valves are described and the requirements and instructions presented in the literature for testing of safety and relief valves are reviewed. Moreover, some testing procedures and related equipment based on pertinent literature are presented. (30 refs., 11 figs., 4 tabs.)

  10. Recognition structure of semipalatinsk residents caused by nuclear explosion tests

    International Nuclear Information System (INIS)

    Authors' team of Hiroshima University and Scientific Research Institute of Radiation Medicine and Ecology (Kazakhstan) has been investigating the health state, exposure route, contents and mental effect of nuclear explosion tests of Semipalatinsk residents through their witness and questionnaire since 2002, to elucidate the humanistic damage of nuclear tests. Reported here is the recognition structure in the title statistically analyzed with use of frequently spoken words in the witness. The audit was performed in 2002-2007 to 994 residents who had experienced ground explosion tests during the period from 1949 to 1962 and were living in 26 villages near the old test site. Asked questions concerning nuclear tests involved such items as still unforgettable matters, dreadful events, regretting things, thought about the test, requests; and matters about themselves, their family, close friends and anything. The frequency of the test site-related words heard in the interview were analyzed with hierarchical clustering and multi-dimensional scaling with a statistic software R for computation and MeCab for morphological analysis. Residents' recognition was found to be of two structures of memory at explosion tests and anger/dissatisfaction/anxiety to the present state. The former contained the frequent words of mushroom cloud, flash, blast, ground tremble and outdoor evacuation, and the latter, mostly anxiety about health of themselves and family. Thus residents have had to be confronted with uneasiness of their health even 20 years after the closure of the test site. (T.T.)

  11. On-site tests on the nuclear power plants

    International Nuclear Information System (INIS)

    On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

  12. Penetration Testing Model for Web sites Hosted in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Nuclear Malaysia web sites has been very crucial in providing important and useful information and services to the clients as well as the users worldwide. Furthermore, a web site is important as it reflects the organisation image. To ensure the integrity of the content of web site, a study has been made and a penetration testing model has been implemented to test the security of several web sites hosted at Nuclear Malaysia for malicious attempts. This study will explain how the security was tested in the detailed condition and measured. The result determined the security level and the vulnerability of several web sites. This result is important for improving and hardening the security of web sites in Nuclear Malaysia. (author)

  13. Dynamic testing of pressure sensing lines in nuclear power plants

    International Nuclear Information System (INIS)

    Commercial nuclear power plants are equipped with instrumentation designed to detect unsafe conditions and, if required, to initiate protective action. The time elapsed between the realization of an unsafe condition and the initiation of protective action is known as the response time of the instrumentation involved. The US Nuclear Regulatory Commission has issued guidelines that advise periodic in situ response-time testing of safety-related instrumentation. No method is currently available for in situ response-time testing of pressure sensing lines (fluid-filled tubes connecting process to pressure transducer). A proposed method of doing just that has been investigated. While the proposed test (the burp test) was found to be impractical, a theoretical description of the sensing line led to the realization that it is probably not necessary to test the response time of sensing lines. Experimental observations backed up this conclusion

  14. Effluent treatment options for nuclear thermal propulsion system ground tests

    International Nuclear Information System (INIS)

    A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests

  15. Handling effluent from nuclear thermal propulsion system ground tests

    International Nuclear Information System (INIS)

    A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests

  16. Parity- and Time-Reversal Tests in Nuclear Physics

    CERN Document Server

    Hertzog, David

    2013-01-01

    Nuclear physics tests of parity- and time-reversal invariance have both shaped the development of the Standard Model and provided key tests of its predictions. These studies now provide vital input in the search for physics beyond the Standard Model. We give a brief review of a few key experimental and theoretical developments in the history of this sub-field of nuclear physics as well as a short outlook, focusing on weak decays, parity-violation in electron scattering, and searches for permanent electric dipole moments of the neutron and neutral atoms.

  17. Parity- and Time-Reversal Tests in Nuclear Physics

    OpenAIRE

    Hertzog, David; Ramsey-Musolf, Michael J.

    2012-01-01

    Nuclear physics tests of parity- and time-reversal invariance have both shaped the development of the Standard Model and provided key tests of its predictions. These studies now provide vital input in the search for physics beyond the Standard Model. We give a brief review of a few key experimental and theoretical developments in the history of this sub-field of nuclear physics as well as a short outlook, focusing on weak decays, parity-violation in electron scattering, and searches for perma...

  18. Capsule irradiation tests of nuclear materials in HANARO

    International Nuclear Information System (INIS)

    Several irradiation capsule (3 instrumented and 2 non-instrumented capsules) were designed, fabricated and successfully irradiated in HANARO CT and IR2 test holes since the first non-instrumented capsule of 96M-01K. Those capsule were designed for the irradiation of the RPV (Reactor Pressure Vessel) material used in Korean PWR nuclear reactors. Various instrumentation techniques including temperature measuring and monitoring, gas controlling, micro-heating and neutron fluence monitoring were also developed for the capsule irradiation system. Through the irradiation tests, the obtained experience and design data will be effectively applied to the capsule design of other nuclear materials. (author)

  19. The initial criticality and nuclear commissioning test program at HANARO

    International Nuclear Information System (INIS)

    The construction of the Korea Multipurpose Research Reactor - HANARO of 3MW, developed by Korea Atomic Energy Research Institute, was completed at the beginning of this year. The first fuel loading began on February 2 1995, and initial criticality was achieved on February 8, when the core had four 18-element assemblies and thirteen 36-element assemblies. The critical control rod position was 600.8 mm which represents excess reactivity of 0.71 $. Currently the nuclear commissioning test is on going under the zero power range. This paper describes the initial criticality approach of the HANARO, and its nuclear commissioning test program. (author)

  20. From Alamogordo to the Nuclear Test-Ban Treaty

    Science.gov (United States)

    Friedlander, Michael

    2008-04-01

    After W.W.II., the U.S. continued its program for the development of nuclear weapons. Winds carried radioactive debris far beyond the Nevada test site, and these fission products were deposited by rain, to enter the human food chain. The isotopes of greatest concern were Sr90 and I131, that, after ingestion, become concentrated in bone and thyroid respectively. There was a growing public anxiety about possible heath hazards posed by radiation from this fallout. In March 1958, the Greater St. Louis Citizens' Committee for Nuclear Information (C.N.I.) was formed. Among the leaders of C.N.I. were E. U. Condon and Barry Commoner. The aim of C.N.I. was ``to collect and distribute in the widest possible manner information which the public requires to understand the present and future problems which arise from potential large-scale use of nuclear weapons in war; testing of nuclear weapons; and nonmilitary uses of nuclear energy.'' In accordance with its objectives, members of C.N.I. gave many nontechnical talks, where we described the various forms of radiation and what was then known about the biological effects of radiation. Some of our members testified at Congressional committee hearings. We published a newsletter, initially titled Nuclear Information, and later Scientist and Citizen. In this presentation, I will describe some of the activities of this idealistic organization.

  1. Nuclear tests of lepton number and CP nonconservation

    International Nuclear Information System (INIS)

    I will discuss two topics, double beta decay and time-reversal-odd nuclear moments, in which important questions of nuclear structure must be addressed. These problems are taken from a growing class of nuclear and atomic experiments in which the special properties of many-body systems are exploited to test properties of elementary particles. Nuclei can serve as filters for interactions by providing kinematic windows where only certain processes can occur and by isolating quantum numbers such as spin, isospin, and parity. In addition, the strengths of interesting interactions can be enhanced through the mixing of nearly degenerate levels in nuclei. However, the most important asset of nuclear and atomic experiments is their precision. For example, experiments searching for T-odd nuclear moments exploit techniques for measuring changes in atomic energies of 10-22 eV. Such precision techniques will play an increasingly important role in particle physics. In the discussion of double beta decay and T-odd nuclear moments it will become clear that important nuclear structure issues must be resolved in order to fully exploit the experimental results. During this talk I will highlight this aspect. 29 references

  2. Why nuclear power failed the market test in the UK

    International Nuclear Information System (INIS)

    The Conservative Party's manifesto for the general election of May 1987 contained two pledges of relevance to the UK electricity supply industry (ESI). These were to privatize the industry; and to continue to support the development of civil nuclear power in the private sector. As anticipated by some independent commentators, in the event these objectives proved incompatible. The costs of nuclear power have long been a vexed issue and UK nuclear costs have been higher than those in many other countries. While most of the UK ESI has now been privatized, nuclear generation remains in the public sector. This article seeks to explore the reasons for this fundamental and politically embarrassing policy reversal, a rarity under three successive Conservative administrations since 1979. It would be incorrect to argue that private ownership and nuclear power are inherently incompatible. Rather the specific - competitive - form of privatization proposed for the UK failed to provide sufficient guarantees for the London capital market. Thus, at least in this specific case, nuclear power failed the market test. The implications of this for the UK nuclear industry have been profound. As a result, the UK case has wider international lessons as the pressures for privatization, liberalization and greater cost transparency bear down upon electric utilities in other countries. (author)

  3. Lightning vulnerability of nuclear explosive test systems at the Nevada Test Site

    International Nuclear Information System (INIS)

    A task force chartered to evaluate the effects of lightning on nuclear explosives at the Nevada Test Site has made several recommendations intended to provide lightning-invulnerable test device systems. When these recommendations have been implemented, the systems will be tested using full-threat-level simulated lightning

  4. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    International Nuclear Information System (INIS)

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ''The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic

  5. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

  6. Dynamic testing of nuclear power plant structures: an evaluation

    International Nuclear Information System (INIS)

    Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants

  7. Modeling and Simulation of a Nuclear Fuel Element Test Section

    Science.gov (United States)

    Moran, Robert P.; Emrich, William

    2011-01-01

    "The Nuclear Thermal Rocket Element Environmental Simulator" test section closely simulates the internal operating conditions of a thermal nuclear rocket. The purpose of testing is to determine the ideal fuel rod characteristics for optimum thermal heat transfer to their hydrogen cooling/working fluid while still maintaining fuel rod structural integrity. Working fluid exhaust temperatures of up to 5,000 degrees Fahrenheit can be encountered. The exhaust gas is rendered inert and massively reduced in temperature for analysis using a combination of water cooling channels and cool N2 gas injectors in the H2-N2 mixer portion of the test section. An extensive thermal fluid analysis was performed in support of the engineering design of the H2-N2 mixer in order to determine the maximum "mass flow rate"-"operating temperature" curve of the fuel elements hydrogen exhaust gas based on the test facilities available cooling N2 mass flow rate as the limiting factor.

  8. Geologic surface effects of underground nuclear testing, Yucca Flat, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    This report presents a new Geographic Information System composite map of the geologic surface effects caused by underground nuclear testing in the Yucca Flat Physiographic Area of the Nevada Test Site, Nye County, Nevada. The Nevada Test Site (NTS) was established in 1951 as a continental location for testing nuclear devices (Allen and others, 1997, p.3). Originally known as the ''Nevada Proving Ground'', the NTS hosted a total of 928 nuclear detonations, of which 828 were conducted underground (U.S. Department of Energy, 1994). Three principal testing areas of the NTS were used: (1) Yucca Flat, (2) Pahute Mesa, and (3) Rainier Mesa including Aqueduct Mesa. Underground detonations at Yucca Flat and Pahute Mesa were typically emplaced in vertical drill holes, while others were tunnel emplacements. Of the three testing areas, Yucca Flat was the most extensively used, hosting 658 underground tests (747 detonations) located at 719 individual sites (Allen and others, 1997, p.3-4). Figure 1 shows the location of Yucca Flat and other testing areas of the NTS. Figure 2 shows the locations of underground nuclear detonation sites at Yucca Flat. Table 1 lists the number of underground nuclear detonations conducted, the number of borehole sites utilized, and the number of detonations mapped for surface effects at Yucca Flat by NTS Operational Area

  9. The consequences of underground nuclear testing in French Polynesia

    International Nuclear Information System (INIS)

    France began atmospheric nuclear testing at Mururoa and Fangataufa atolls in the South Pacific in July 1966. Following international protest, atmospheric testing ceased in August 1970. In late 1995, an International Geomechanical Commission (IGC) was created to assess the short- and long-term effects of underground nuclear testing on the stability and hydrology of Mururoa and Fangataufa. With the aid of its consultants, the Commission sought to develop its own understanding of the mechanics and consequences of the underground nuclear tests. It carried out extensive numerical analyses of shock wave effects, seismic wave propagation, slope stability and pre- and post-test hydrology. However, in its studies, the IGC was constrained to use the data made available to it by the French authorities. The Commission's report (International Geomechanical Commission 1998) has been submitted to the French Government. This article draws heavily on parts of that report. The Commission's observations and analyses show that there has been no apparent change, on the atoll scale, to the overall mechanical stability of either atoll as a consequence of the underground nuclear tests. The main observable consequences of the tests are underwater slope failures, open fractures on the rim surface and surface settlements. The fractures visible on the surface are generally associated with subsurface slope displacements and occur only in the carbonates. There is no evidence that slope failures or settlements have occurred in the underlying volcanics. There has been no significant change in the long-term (beyond 500 years) hydrology of either atoll. The IGC estimates that the long-term change in the natural groundwater flow will be no more than 1%. There are, however, significant short-term changes locally around the test sites, which are briefly outlined

  10. Prediction of ground motion from nuclear weapons tests at NTS

    International Nuclear Information System (INIS)

    Ground motion data from underground nuclear detonations during FY78 were added to data from earlier detonations; the data were used to formulate a tentative equation for predicting ground motion at the Nevada Test Site. Additional measurements to explore an unexplained seismic anomaly in Jackass Flats are described. Methods used in automatic processing of ground motion data are explained

  11. A nuclear power plant certification test plan and checklist

    International Nuclear Information System (INIS)

    Regulations within the nuclear industry are requiring that all reference plant simulators be certified prior to or during 1991. A certification test plan is essential to ensure that this goal is met. A description of each step in the certification process is provided in this paper, along with a checklist to help ensure completion of each item

  12. Accurate location of nuclear explosions at Azgir, Kazakhstan, from satellite images and seismic data: Implications for monitoring decoupled explosions

    Science.gov (United States)

    Sykes, Lynn R.; Deng, Jishu; Lyubomirskiy, Paul

    1993-09-01

    The 10 largest tamped nuclear explosions detonated by the Former Soviet Union in and near two salt domes near Azgir were relocated using seismic data and the locations of shot points on a SPOT satellite image taken in 1988. Many of the shot points are clearly recognized on the satellite image and can be located with an accuracy of 60 m even though testing was carried out at those points many years earlier, i. e. between 1966 and 1979. Onsite inspections and a local seismic monitoring network combined with our accurate locations of previous explosions would insure that any cavities that remain standing from those events could not be used for undetected decoupled nuclear testing down to a very small yield. Since the Azgir area, like much of the Pre-Caspian depression, is arid, it would not be a suitable place for constructing large cavities in salt by solution mining and then using them for clandestine nuclear testing.

  13. Overview of seismic reliability proof test of nuclear power facilities

    International Nuclear Information System (INIS)

    This report overviewed seismic reliability proof test of nuclear power facilities, which had been performed for 25 years until March 2004 to confirm seismic safety and safety margin of nuclear power facilities by seismic test of scale model equipment akin to full size using the Tadotsu Vibration Exciter. Test results were outlined to understand test objective, test model, earthquake input condition, test items and test results. Fifteen items were tested for verification tests of seismic reliability of reactor components or system against basic ground motion S1 and S2, and later validation of new technology (heavy components with energy absorbing support) and confirmation of functional limit of PCCV/RCCV and piping system. This report might contribute to understand safety function of important equipment against new basic earthquake ground motion Ss, and limit of strength/function or damage mode of equipment against earthquake beyond Ss, which were requested by 'new seismic design review guide' updated in September 2006 based on latest technical knowledge. (T. Tanaka)

  14. Drop testing of the Westinghouse fresh nuclear fuel package

    International Nuclear Information System (INIS)

    The Westinghouse Columbia Fuel Fabrication Facility has decided to develop and certify a new fresh fuel package design (type A, fissile) that has the capability to transport more highly enriched fuel than was previously possible. A prototype package was tested in support of the Safety Analysis Report of the Packaging (SARP). This paper provides detailed information on the tests and test results. A first prototype test was carried out at the STF, and the design did not give the safety margin that Westinghouse wanted for their containers. The data from the test were used to redesign the connection between the clamping frame and the pressure pad, and the tests were reinitiated. Three packages were then tested at the STF. All packages met the acceptance criteria and acceleration information was obtained that provided an indication of the behavior of the cradle and strongback which holds the fuel assemblies and nuclear poison in place. (J.P.N.)

  15. Nuclear performance analyses for HCPB test blanket modules in ITER

    International Nuclear Information System (INIS)

    Neutronic, shielding and activation analyses have been performed for recent design variants of the Helium Cooled Pebble Bed (HCPB) test blanket module (TBM) in ITER on the basis of 3D Monte Carlo calculations. The main objective has been to assess and optimise the nuclear performance of the HCPB test blanket modules in terms of the tritium generation, the nuclear heating and the radiation shielding and provide, among others, the data required for the engineering design of the test modules. The shielding efficiency of the TBM system was shown to be sufficient to allow access of work personnel to the port extension after a waiting time of 10 days after shut down as required by ITER. The activation analyses provided the afterheat and activation data for quality assured safety analyses assuming a representative irradiation scenario

  16. Guidelines for inservice testing at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, P.

    1995-04-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

  17. Guidelines for inservice testing at nuclear power plants

    International Nuclear Information System (INIS)

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

  18. Micro-specimen testing techniques for evaluating nuclear reactor materials

    International Nuclear Information System (INIS)

    In the initial construction of nuclear power plant nuclear materials not only have to be high quality in mechanical properties and fracture resistant characteristics, but also considerations have to be given to weakness cause and continued safe operation of power reactor. Recognizing the importance of integrity evaluation test material samples are provided under monitoring program in reactor for evaluation of reactor material property. But because of limited space and necessity of a homogeneous irradiation environment a very limited quantity of micro specimen is provided. The existing test method of toughness property and fracture resistance requires pre-determined size specimen. Therefore, it is very difficult to evaluate those properties by limited micro-specimen provided under monitoring program. In this paper the test technologies of micro-specimen, which can be utilized to evaluate material integrity of reactors in operation, are reviewed. (Hong, J. S.)

  19. Testing the predictive power of nuclear mass models

    International Nuclear Information System (INIS)

    A number of tests are introduced which probe the ability of nuclear mass models to extrapolate. Three models are analyzed in detail: the liquid drop model, the liquid drop model plus empirical shell corrections and the Duflo-Zuker mass formula. If predicted nuclei are close to the fitted ones, average errors in predicted and fitted masses are similar. However, the challenge of predicting nuclear masses in a region stabilized by shell effects (e.g., the lead region) is far more difficult. The Duflo-Zuker mass formula emerges as a powerful predictive tool

  20. Testing the predictive power of nuclear mass models

    Energy Technology Data Exchange (ETDEWEB)

    Mendoza-Temis, J.; Morales, I. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apdo. Postal 70-543, Mexico 04510 D.F. (Mexico); Barea, J. [Center for Theoretical Physics, Sloane Physics Laboratory, Yale University, PO Box 208120, New Haven, CT 06520-8120 (United States); Frank, A. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apdo. Postal 70-543, Mexico 04510 D.F. (Mexico); Hirsch, J.G. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apdo. Postal 70-543, Mexico 04510 D.F. (Mexico)], E-mail: hirsch@nucleares.unam.mx; Vieyra, J.C. Lopez [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apdo. Postal 70-543, Mexico 04510 D.F. (Mexico); Van Isacker, P. [Grand Accelerateur National d' Ions Lourds, CEA/DSM-CNRS/IN2P3, BP 55027, F-14076 Caen cedex 5 (France); Velazquez, V. [Facultad de Ciencias, Universidad Nacional Autonoma de Mexico, Apdo. Postal 70-543, Mexico 04510 D.F. (Mexico)

    2008-11-01

    A number of tests are introduced which probe the ability of nuclear mass models to extrapolate. Three models are analyzed in detail: the liquid drop model, the liquid drop model plus empirical shell corrections and the Duflo-Zuker mass formula. If predicted nuclei are close to the fitted ones, average errors in predicted and fitted masses are similar. However, the challenge of predicting nuclear masses in a region stabilized by shell effects (e.g., the lead region) is far more difficult. The Duflo-Zuker mass formula emerges as a powerful predictive tool.

  1. Resettlement of Bikini Atoll U.S. Nuclear Test Site

    International Nuclear Information System (INIS)

    The US conducted a nuclear testing program at Bikini and Enewetak Atolls in the Marshall Islands from 1946 through 1958. Several atolls, including Bikini, were contaminated as a result of the nuclear detonations. Since 1974 the authors have conducted an extensive research and monitoring program to determine the radiological conditions at the atolls, identify the critical radionuclides and pathways, estimate the radiological dose to current or resettling populations, and develop remedial measures to reduce the dose to atoll populations. This paper describes exposure pathways and radionuclides; composition of atoll soils; radionuclide transport and dose estimates; remedial measures; and reduction in dose from a combined option

  2. Semblance analysis to assess GPR data from a five-year forensic study of simulated clandestine graves

    Science.gov (United States)

    Booth, Adam D.; Pringle, Jamie K.

    2016-02-01

    Ground penetrating radar (GPR) surveys have proven useful for locating clandestine graves in a number of forensic searches. There has been extensive research into the geophysical monitoring of simulated clandestine graves in different burial scenarios and ground conditions. Whilst these studies have been used to suggest optimum dominant radar frequencies, the data themselves have not been quantitatively analysed to-date. This study uses a common-offset configuration of semblance analysis, both to characterise velocity trends from GPR diffraction hyperbolae and, since the magnitude of a semblance response is proportional to signal-to-noise ratio, to quantify the strength of a forensic GPR response. 2D GPR profiles were acquired over a simulated clandestine burial, with a wrapped-pig cadaver monitored at three-month intervals between 2008 and 2013 with GPR antennas of three different centre-frequencies (110, 225 and 450 MHz). The GPR response to the cadaver was a strong diffraction hyperbola. Results show, in contrast to resistivity surveys, that semblance analysis have little sensitivity to changes attributable to decomposition, and only a subtle influence from seasonality: velocity increases (0.01-0.02 m/ns) were observed in summer, associated with a decrease (5-10%) in peak semblance magnitude, SM, and potentially in the reflectivity of the cadaver. The lowest-frequency antennas consistently gave the highest signal-to-noise ratio although the grave was nonetheless detectable by all frequencies trialled. These observations suggest that forensic GPR surveys could be undertaken with little seasonal hindrance. Whilst GPR analysis cannot currently provide a quantitative diagnostic proxy for time-since-burial, the consistency of responses suggests that graves will remain detectable beyond the five years shown here.

  3. Review of Nuclear Thermal Propulsion Ground Test Options

    Science.gov (United States)

    Coote, David J.; Power, Kevin P.; Gerrish, Harold P.; Doughty, Glen

    2015-01-01

    High efficiency rocket propulsion systems are essential for humanity to venture beyond the moon. Nuclear Thermal Propulsion (NTP) is a promising alternative to conventional chemical rockets with relatively high thrust and twice the efficiency of highest performing chemical propellant engines. NTP utilizes the coolant of a nuclear reactor to produce propulsive thrust. An NTP engine produces thrust by flowing hydrogen through a nuclear reactor to cool the reactor, heating the hydrogen and expelling it through a rocket nozzle. The hot gaseous hydrogen is nominally expected to be free of radioactive byproducts from the nuclear reactor; however, it has the potential to be contaminated due to off-nominal engine reactor performance. NTP ground testing is more difficult than chemical engine testing since current environmental regulations do not allow/permit open air testing of NTP as was done in the 1960's and 1970's for the Rover/NERVA program. A new and innovative approach to rocket engine ground test is required to mitigate the unique health and safety risks associated with the potential entrainment of radioactive waste from the NTP engine reactor core into the engine exhaust. Several studies have been conducted since the ROVER/NERVA program in the 1970's investigating NTP engine ground test options to understand the technical feasibility, identify technical challenges and associated risks and provide rough order of magnitude cost estimates for facility development and test operations. The options can be divided into two distinct schemes; (1) real-time filtering of the engine exhaust and its release to the environment or (2) capture and storage of engine exhaust for subsequent processing.

  4. Nuclear-waste-package materials degradation modes and accelerated testing

    International Nuclear Information System (INIS)

    This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

  5. Thermal measurements in the nuclear winter fire test

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, M.E.; Keltner, N.R.; Kent, L.A.

    1989-01-01

    In March, 1987, a large open pool fire test was performed to provide test measurements to help define the thermal characteristics of large open pool fires and estimates of the smoke source term for the nuclear winter (global effects) scenario. This report will present the results of the thermal measurements as well as comparisons with previous test results. These measurements included flame temperatures, heat fluxes to a variety of calorimeters, and gas velocities in the lower flame regions. 13 refs., 76 figs., 7 tabs.

  6. Smart built-in test for nuclear thermal propulsion

    International Nuclear Information System (INIS)

    Smart built-in test (BIT) technologies are envisioned for nuclear thermal propulsion spacecraft components which undergo constant irradiation and are therefore unsafe for manual testing. Smart BIT systems of automated/remote type allow component and system tests to be conducted; failure detections are directly followed by reconfiguration of the components affected. The 'smartness' of the BIT system in question involves the reduction of sensor counts via the use of multifunction sensors, the use of components as integral sensors, and the use of system design techniques which allow the verification of system function beyond component connectivity

  7. Rolling test of turbine generator by non-nuclear steam

    International Nuclear Information System (INIS)

    The object and procedure of rolling turbine generator test by non-nuclear steam in Qinshan NPP are presented. The steam source of rolling test is compared and chosen. The steam quantity during the rolling test is simply calculated. The limits of parameters of the test and the preparing for rolling of turbine generator are introduced. Procedures of rolling test are divided into three stage of speed: 600 r/min, 1200 r/min, 3000 r/min. Parameters measured as a result of rolling test, such as absolute vibration of axle, metal temperature of bearings, temperature of oil from the exit of bearings and vacuity of condenser etc, show that the design, manufacture, installation and speed control of turbine generator are satisfactory

  8. 78 FR 35330 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2013-06-12

    ... COMMISSION Initial Test Programs for Water-Cooled Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG), 1.68, ``Initial Test Programs for Water-Cooled Nuclear Power Plants... Initial Test Programs (ITPs) for light water cooled nuclear power plants. ADDRESSES: Please refer...

  9. Space exploration initiative candidate nuclear propulsion test facilities

    Science.gov (United States)

    Baldwin, Darrell; Clark, John S.

    1993-01-01

    One-page descriptions for approximately 200 existing government, university, and industry facilities which may be available in the future to support SEI nuclear propulsion technology development and test program requirements are provided. To facilitate use of the information, the candidate facilities are listed both by location (Index L) and by Facility Type (Index FT). The included one-page descriptions provide a brief narrative description of facility capability, suggest potential uses for each facility, and designate a point of contact for additional information that may be needed in the future. The Nuclear Propulsion Office at NASA Lewis presently plans to maintain, expand, and update this information periodically for use by NASA, DOE, and DOD personnel involved in planning various phases of the SEI Nuclear Propulsion Project.

  10. ASEAN and the commitment to end nuclear testing

    International Nuclear Information System (INIS)

    The Association of Southeast Asian Nations (ASEAN) is a regional political and economic organization. It was established on 8 August 1967 by Indonesia, Malaysia, the Philippines, Singapore and Thailand. Brunei Darussalam joined in 1984, Viet Nam in 1995, Laos and Myanmar in 1997 and Cambodia in 1999. ASEAN aims to accelerate economic growth, social progress and cultural development in its Member States and to promote regional peace and stability. All ASEAN States are parties to the Nuclear Non-Proliferation Treaty (NPT). The NPT aims to prevent the spread of nuclear weapons and weapons technology, and to further the goal of nuclear disarmament. It also promotes international cooperation in the peaceful uses of nuclear energy. The ten ASEAN countries are all Member States of the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO). They all signed the CTBT early on, some on the very first day that it opened for signature on 24 September 1996. But four have yet to ratify the Treaty: Brunei Darussalam, Indonesia, Myanmar and Thailand. Indonesia's ratification is particularly important as it is one of those States whose ratification is required for the Treaty's entry into force.

  11. Maintaining non-nuclear weapon status

    International Nuclear Information System (INIS)

    Among the some 170 sovereign states in the world, five are legally recognized as nuclear weapon states (NWS) under the terms of the 1968 Non-Proliferation Treaty (NPT). Six countries (Argentina, Brazil, India, Israel, Pakistan, and South Africa) are counted as threshold states: they possess sizeable unsafeguarded nuclear facilities or have passed the brink of a nuclear test or of clandestine weapon production. Six other countries (Iran, Iraq, Libya, Taiwan, and North and South Korea) have been suspected periodically of either considering the nuclear weapon option or of working secretly on the development of weapons. Thus, about 150 non-nuclear weapon states (NNWS) remain which neither possess nuclear weapons nor strive to acquire them. These states are distributed throughout the globe and encompass highly industrialized as well as underdeveloped countries, liberal democracies, socialist states, sheikdoms and dictatorships. Some NNWS face acute military threats; other are far removed from the quarrels of the world, as in the case of some remote fortunate islands. Furthermore, NNWS may be members of nuclear-umbrella alliances or may have opted for a policy of neutrality or non-alignment

  12. Testing of Small Graphite Samples for Nuclear Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Julie Chapman

    2010-11-01

    Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

  13. Seismological analysis of the fourth North Korean nuclear test

    Science.gov (United States)

    Hartmann, Gernot; Gestermann, Nicolai; Ceranna, Lars

    2016-04-01

    The Democratic People's Republic of Korea has conducted its fourth underground nuclear explosions on 06.01.2016 at 01:30 (UTC). The explosion was clearly detected and located by the seismic network of the International Monitoring System (IMS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Additional seismic stations of international earthquake monitoring networks at regional distances, which are not part of the IMS, are used to precisely estimate the epicenter of the event in the North Hamgyong province (41.38°N / 129.05°E). It is located in the area of the North Korean Punggye-ri nuclear test site, where the verified nuclear tests from 2006, 2009, and 2013 were conducted as well. The analysis of the recorded seismic signals provides the evidence, that the event was originated by an explosive source. The amplitudes as well as the spectral characteristics of the signals were examined. Furthermore, the similarity of the signals with those from the three former nuclear tests suggests very similar source type. The seismograms at the 8,200 km distant IMS station GERES in Germany, for example, show the same P phase signal for all four explosions, differing in the amplitude only. The comparison of the measured amplitudes results in the increasing magnitude with the chronology of the explosions from 2006 (mb 4.2), 2009 (mb 4.8) until 2013 (mb 5.1), whereas the explosion in 2016 had approximately the same magnitude as that one three years before. Derived from the magnitude, a yield of 14 kt TNT equivalents was estimated for both explosions in 2013 and 2016; in 2006 and 2009 yields were 0.7 kt and 5.4 kt, respectively. However, a large inherent uncertainty for these values has to be taken into account. The estimation of the absolute yield of the explosions depends very much on the local geological situation and the degree of decoupling of the explosive from the surrounding rock. Due to the missing corresponding information, reliable magnitude-yield estimation for the

  14. Summary of Numerical Modeling for Underground Nuclear Test Monitoring Symposium

    International Nuclear Information System (INIS)

    This document contains the Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium held in Durango, Colorado on March 23-25, 1993. The symposium was sponsored by the Office of Arms Control and Nonproliferation of the United States Department of Energy and hosted by the Source Region Program of Los Alamos National Laboratory. The purpose of the meeting was to discuss state-of-the-art advances in numerical simulations of nuclear explosion phenomenology for the purpose of test ban monitoring. Another goal of the symposium was to promote discussion between seismologists and explosion source-code calculators. Presentation topics include the following: numerical model fits to data, measurement and characterization of material response models, applications of modeling to monitoring problems, explosion source phenomenology, numerical simulations and seismic sources

  15. Production and testing of tubes for nuclear boiler steam generators

    International Nuclear Information System (INIS)

    Vallourec, second pipe manufacturer in Europe, has developed a workshop for the production of nuclear heat exchanger tubes in its Montbard plant. This workshop, by its special construction, production engineering and handling procedures, has attained nuclear standards and can produce U-bended tubes from diameter 12 to 25 mm with a maximum length of 36 meters. Its annual out-put is 1.500.000 meters. The final dimensions are obtained by a cold rolling procedure, followed by an outside and inside degreasing, a solution annealing in a controlled atmosphere continuous type furnace, a surface grinding and an inside surface conditionning. The non-destructive tests: eddy currents, ultrasonic tests and thickness mesures are recorded on a single tube basis. The curving and packing procedures have been specially developed for this production

  16. Nuclear waste package materials testing report: basaltic and tuffaceous environments

    International Nuclear Information System (INIS)

    The disposal of high-level nuclear wastes in underground repositories in the continental United States requires the development of a waste package that will contain radionuclides for a time period commensurate with performance criteria, which may be up to 1000 years. This report addresses materials testing in support of a waste package for a basalt (Hanford, Washington) or a tuff (Nevada Test Site) repository. The materials investigated in this testing effort were: sodium and calcium bentonites and mixtures with sand or basalt as a backfill; iron and titanium-based alloys as structural barriers; and borosilicate waste glass PNL 76-68 as a waste form. The testing also incorporated site-specific rock media and ground waters: Reference Umtanum Entablature-1 basalt and reference basalt ground water, Bullfrog tuff and NTS J-13 well water. The results of the testing are discussed in four major categories: Backfill Materials: emphasizing water migration, radionuclide migration, physical property and long-term stability studies. Structural Barriers: emphasizing uniform corrosion, irradiation-corrosion, and environmental-mechanical testing. Waste Form Release Characteristics: emphasizing ground water, sample surface area/solution volume ratio, and gamma radiolysis effects. Component Compatibility: emphasizing solution/rock, glass/rock, glass/structural barrier, and glass/backfill interaction tests. This area also includes sensitivity testing to determine primary parameters to be studied, and the results of systems tests where more than two waste package components were combined during a single test

  17. Thyroid cancer following nuclear tests in French Polynesia

    OpenAIRE

    De Vathaire, F.; Drozdovitch, V.; Brindel, P.; Rachedi, F.; Boissin, J-L; Sebbag, J.; Shan, L; Bost-Bezeaud, F.; Petitdidier, P; Paoaafaite, J.; Teuri, J; Iltis, J; Bouville, A.; Cardis, E; Hill, C.

    2010-01-01

    BACKGROUND: Between 1966 and 1974, France conducted 41 atmospheric nuclear tests in Polynesia, but their potential health effects have not previously been investigated. METHODS: In a case-control study, we compared the radiation exposure of almost all the French Polynesians diagnosed with differentiated thyroid carcinoma between 1981 and 2003 (n = 229) to the exposure of 373 French Polynesian control individuals without cancer from the general population. Radiation exposures were estimated us...

  18. Forensic Medicine: Age Written in Teeth by Nuclear Bomb Tests

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence Livermore National Laboratory

    2005-05-04

    Establishing the age of individuals is an important step in identification and a frequent challenge in forensic medicine. This can be done with high precision up to adolescence by analysis of dentition, but establishing the age of adults has remained difficult. Here we show that measuring {sup 14}C from nuclear bomb tests in tooth enamel provides a sensitive way to establish when a person was born.

  19. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal to determine compliance with specifications.

  20. Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

    1997-01-01

    A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs.

  1. Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

    International Nuclear Information System (INIS)

    A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs

  2. Module Testing Techniques for Nuclear Safety Critical Software Using LDRA Testing Tool

    International Nuclear Information System (INIS)

    The safety critical software in the I and C systems of nuclear power plants requires high functional integrity and reliability. To achieve those requirement goals, the safety critical software should be verified and tested according to related codes and standards through verification and validation (V and V) activities. The safety critical software testing is performed at various stages during the development of the software, and is generally classified as three major activities: module testing, system integration testing, and system validation testing. Module testing involves the evaluation of module level functions of hardware and software. System integration testing investigates the characteristics of a collection of modules and aims at establishing their correct interactions. System validation testing demonstrates that the complete system satisfies its functional requirements. In order to generate reliable software and reduce high maintenance cost, it is important that software testing is carried out at module level. Module testing for the nuclear safety critical software has rarely been performed by formal and proven testing tools because of its various constraints. LDRA testing tool is a widely used and proven tool set that provides powerful source code testing and analysis facilities for the V and V of general purpose software and safety critical software. Use of the tool set is indispensable where software is required to be reliable and as error-free as possible, and its use brings in substantial time and cost savings, and efficiency

  3. Water and heat flow simulation after underground nuclear test

    International Nuclear Information System (INIS)

    Based on the information about the damaged zone and local hydraulic data of CHESHIRE which is an underground nuclear test at the Nevada Test Site, a model was developed to simulate water and heat transport process using FEFLOW software. The temperature descending curve of the melt glass was acquired. The simulated temperature was consistent with the measured data. According to the simulation result, the temperature descending process obeys an exponent decay function, and the groundwater convection mainly affects the melt glass temperature descending process. (authors)

  4. Seismic test of local control panel for nuclear power plant

    International Nuclear Information System (INIS)

    The safety related equipment installed in Nuclear Power Plant are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Regulatory Guide 1.100 and IEEE Std. 344. The local control panel is a safety related equipment which provide operators with control, display and monitoring for plant operating conditions. This paper describes test procedure for seismic qualification test of local control panel which is installed in Ulchin units 3 and 4. (author)

  5. Radionuclide distribution in a nuclear test cavity: the baseball event

    International Nuclear Information System (INIS)

    In 1994 two holes were drilled into the cavity formed in 1981 by the underground nuclear test named Baseball. An extensive set of side wall samples were collected in these holes. We have analyzed the samples for tritium and for gamma-emitting radionuclides (both fission products and neutron activation products). It appears that the distribution pattern of these radioactive materials, established at the time of the detonation, have persisted even though the cavity has been under water for 13 years. These findings are discussed in the context of radionuclide migration and groundwater contamination at the Nevada Test Site. (orig.)

  6. DIGITAL RADIOGRAPHY OF SPECIAL NUCLEAR MATERIAL TEST PACKAGES

    Energy Technology Data Exchange (ETDEWEB)

    HOWARD, BOYD

    2006-02-02

    The purpose of this document is to provide a brief introduction to digital radiography (DR), and a description of the DR configuration that was used to radiographically image the Special Nuclear Material (SNM) Test Packages before and after function tests that have been conducted. Also included are (1) Attachment 1, a comprehensive index that describes at which phase of the certification process that digital radiographic images were acquired, (2) digital radiographic images of each of the six packages at various stages of the certification process, and (3) Attachment 2, imaging instructions, that specify the setup procedures and detailed parameters of the DR imaging methodology that were used.

  7. Nuclear test - The French nuclear strike force in the 21. century: challenges, ambitions and strategy

    International Nuclear Information System (INIS)

    This bibliographical note presents a book in which the author, after having recalled the history of the French nuclear force since the first nuclear test in 1960, and outlined the fact that France has been living under the protection of its own nuclear deterrence force since that date, presents the components of this nuclear strike force with its four nuclear submarines equipped to launch new generation missiles, its fifty fighter bomber aircraft equipped with the ASMP-A missile. He presents and discusses the mission of this nuclear force, discusses the relevancy of the deterrence strategy in the present context, and the significance of such a strategy for a European country like France. He wanders whether this strike force is still affordable for our country, which can be its benefits, whether this arsenal remains useful as it has been designed in the Cold War context. He also discusses the disarmament perspectives in an unsteady international environment where power and arms race logics prevail again

  8. RSM development for nuclear safety analysis. A test problem

    International Nuclear Information System (INIS)

    In any study of nuclear reactor safety the ultimate aim is to produce estimates of accident consequence probabilities as a function of the uncertainties in the physical and operational variables governing the accident behaviour. The present study has been performed as a test case for the routines to implement in the library and as a methodological investigation of the response surface methodology techniques. As a test case, an analytical function has been chosen, in this exercice, to play the role of a nuclear safety code. This choice enable us to perform an extensive analysis of the artificial data produced, without spending considerable computer time. The study can be divided into the following steps: choice of the test function, choice of the models, experimental design, parameter estimation, propagation of input uncertainties on output probability distribution function through the test function and the models, comparison of the models with the test function over the whole variable space. This note principally focuses the discussion on the results

  9. The environmental and sanitary effects of nuclear weapons tests made by France between 1960 and 1996 and comparison elements with the tests of others great nuclear countries

    International Nuclear Information System (INIS)

    For the most of nuclear test sites, in a condensed way, elements of information and analysis about the environmental and sanitary effects of nuclear explosions are given. This report gives a precise view about this question. (N.C.)

  10. Eddy current testing on structures of nuclear-grade PGX graphite for acceptance test in HTTR

    International Nuclear Information System (INIS)

    Acceptance test with eddy current testing is planned to be applied to the core support graphite structures made of PGX graphite, nuclear-grade near-isotropic graphite, in the HTTR. The eddy current testing widely applied to metallic components is not applicable to porous graphite materials due to different characteristics compared with metallic ones. Hence, the eddy current testing method for the fine-grained, nuclear-grade IG-110 graphite had been established. However, this method is also not applicable to the PGX graphite owing to the different flaw detectability because the PGX consists of larger grains and pores than the IG-110. Therefore the eddy current testing method and condition for the PGX graphite were established on the bases of the experimental investigation. (author)

  11. Nuclear weapon tests on the testing ground near Semipalatinsk and health of communities of Altay region

    International Nuclear Information System (INIS)

    The comparative analysis of morbidity, mortality and invalidization of the population of Altay region and other regions of West Siberia. It was found that in recent years in spite of a more favorable ecologic situation in this area the level of morbidity (hematological disorders, cardiovascular disorders, urinary diseases), mortality from infectious, parasitic, pulmonary diseases and malignant tumors and invalidisation of the population increased. The main cause of this is supposed to be the consequences of nuclear weapon tests in the atmosphere in 1949-1962 on the testing ground near Semipalatinsk at the border of Altay region. The data on repeated pollutions by the products of nuclear disintegration in Altay region are reported

  12. Dynamic analysis and qualification test of nuclear components

    International Nuclear Information System (INIS)

    This report contains the study on the dynamic characteristics of Wolsung fuel rod and on the dynamic balancing of rotating machinery to evaluate the performance of nuclear reactor components. The study on the dynamic characteristics of Wolsung fuel rod was carried out by both experimental and theoretical methods. Forced vibration testing of actual Wolsung fuel rod using sine sweep and sine dwell excitation was conducted to find the dynamic and nonlinear characteristics of the fuel rod. The data obtained by the test were used to analyze the nonlinear impact characteristics of the fuel rod which has a motion-constraint stop in the center of the rod. The parameters used in the test were the input force level of the exciter, the clearance gap between the fuel rod and the motion constraints, and the frequencies. Test results were in good agreement with the analytical results

  13. Reactor design of the SP-100 nuclear assembly test

    International Nuclear Information System (INIS)

    The Nuclear Assembly Test is currently being designed to demonstrate the performance characteristics of a 100-kWe version of the power source for the SP-100 Generic Flight System. Particular emphasis will be placed upon the operation of the prototypical ground test reactor under conditions of high-working temperatures and long life. The key features of the reactor include a small, compact core with component materials consisting of refractory metals and alloys. Because of the unique features of the SP-100 system, extensive use is made of Monte Carlo methods in the design and analysis of the reactor configuration. In addition, detailed testing of the reactor design has been carried out in the Zero Power Physics Reactor facility to provide calibration factors for the principal performance parameters. The key features of the test reactor design are described in this paper

  14. History of creation of Semipalatinsk test nuclear site. Chapter 1

    International Nuclear Information System (INIS)

    In 1949 August USSR's Government adopted decision about creation of nuclear site with conditional name Uchebnyj polygon 2. For its building was chosen territory in 140 km from Semipalatinsk city. Semipalatinsk test site consists of the land of three regions: Semipalatinsk, Pavlodar, Karaganda and it occupies 18,500 km2 of fertile land, rich with minerals. Now this territory was alienated from national using. Polygon was complex object and it incorporated three main zones: Opytnoe Pole, zone of radiation safety, site Sh. Opytnoe Pole was equipped by special constructions ensuring nuclear test conducting, its observing and registration of physical measurements and occupied 2,300 km2. Around of the Opytnoe Pole is situated zone of radiation safety with area 45 thousand ha. Site Sh was situated in 14 km from center of Opytnoe Pole and it was intended for distribution of individual protection devices, dosimeters and for conducting of dis-activation and sanitary works. History of the site creation is connected with building of Kurchatov city. In dozen and hundred of kilometers from Kurchatov city there were top secret objects: site Balapan with total area 100,000 ha intended for conducting of nuclear tests in wells with threshold capacity 100-200 kt. Here simultaneously with main problems on the site the military-applied works were conducted on mechanics, physics of combustion, simulation of Earthquakes and determination of seismic stability of buildings and constructions. Research site Degelen with total area 33,100 ha which has been used for underground testing of nuclear charges with small capacity. Site 10 one of large research technical complex on which two reactor units were installed. Main tasks of the complex were as follows: high-temperature fuel materials testing, conducting of fundamental researches in field of physics of fissile products, thermal physics and gas hydrodynamics. On site M a laboratory base for radiochemical, radiological and chemical researches

  15. Upgrade and Development of Nuclear Data Production Test Facility

    International Nuclear Information System (INIS)

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: (1) upgrade the electron linac, (2) collimators inside the TOF beam pipe, (3) the development and installation of an automatic sample changer, (4) the extension of the TOF beam line, and (5) the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students

  16. Head-end demonstration test for nuclear fuel reprocessing plant. Outline of the test results

    International Nuclear Information System (INIS)

    Japan Nuclear Fuel Ltd. (JNFL) is now constructing a nuclear fuel reprocessing plant (Rokkasho Reprocessing Plant) at Rokkasho-mura. Concerning the head-end process, which includes shearing and dissolving processes for spent fuel and rinsing processes for upper and lower end-pieces of spent fuel assemblies and chopped fuel rods, a full-scale mock-up test facility was constructed and functional and performance tests were performed using a dummy fuel assembly and chopped fuel rods. This paper summarizes results the tests conducted from 1988 to 1993 by Mitsubishi Heavy Industries, Ltd. (MHI). The head-end demonstration test (HEDT) facility includes five components: tilting crane, shearing machine, dissolver, hull rinser and end-piece rinser. The design of these components manufactured by MHI is based on SGN technology. The suitability of the design, the functional reliability, the operability, the controllability and the maintainability were evaluated through functional tests such as an operation test, a shearing test, a transfer test, a heating and cooling test and a remote maintenance test under cold (non radioactive) conditions. The test results were satisfactory. The component performance data and our manufacturing and operation experience will greatly facilitate the final design process and support the choice of operational parameters for these head-end components of the Rokkasho Reprocessing Plant. (author)

  17. 78 FR 67206 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-11-08

    ... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear...-Related Actuators in Nuclear Power Plants.'' This RG is being revised to provide applicants and licensees with the most current information on testing safety-related actuators in nuclear power plants. This...

  18. 78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-05-01

    ... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear..., ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' DG-1235 is proposed Revision 1 of RG... in Nuclear Power Plants'' is temporarily identified by its task number, DG-1235. The DG-1235...

  19. 77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2012-12-07

    ... COMMISSION Initial Test Programs for Water-Cooled Nuclear Power Plants AGENCY: Nuclear Regulatory Commission...-Cooled Nuclear Power Plants.'' This guide describes the general scope and depth that the staff of the NRC considers acceptable for Initial Test Programs (ITPs) for light water cooled nuclear power plants....

  20. Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Friesen, H.N.

    1995-06-01

    Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

  1. The nondestructive testing of tubes and pipes for nuclear application

    International Nuclear Information System (INIS)

    The directive of the Reactor Safety Commission demands for all materials which are provided for the pressure bearing enclosure of the refrigerant a nondestructive testing with sufficient sensibility. The specification 3201.1 for nuclear application as well as company-internal rules of important manufacturers regulate the requirements derived from the above direction for the NDT of tubes and pipes. For an objective and reproducible testing, equipments with defined characteristics are employed, based on internal specifications, testing equipments are fabricated and then checked with a special computerized test system. Moreover probes are controlled with regard to their acoustic and electric properties. The NDT of heat exchanger tubes and of pipes is given here as an example: Heat exchanger tubes: The tests include the inspection of longitudinal and transverse defects, wall thickness, dimension and tightness. In connection with the NDT, defect catalogues are set up. By this means the chosen test sensitivity is verified, and so the high quality of the tubes is assured. Specially developed eddy-current methods prove that such tested tubes are free of corrosion-causing phases. Pipes: The pipes are tested for longitudinal and transverse defects, for laminations and for wall thickness. To fulfil the demand for an objective and reproducible testing, there was developed and installed an automatic, computer-controlled ultrasonic equipment with 40 probes. Development trends: For the NDT of heat exchanger and boiler tubes an electrodynamic excited ultrasonic test system is evolved which is also able to test curved and installed tubes. The sophisticated testing technology is completed by a qualified education and training of NDT personnel. (orig.)

  2. Low Cost Nuclear Thermal Rocket Cermet Fuel Element Environment Testing

    Science.gov (United States)

    Bradley, David E.; Mireles, Omar R.; Hickman, Robert R.

    2011-01-01

    Deep space missions with large payloads require high specific impulse (Isp) and relatively high thrust in order to achieve mission goals in reasonable time frames. Conventional, storable propellants produce average Isp. Nuclear thermal rockets (NTR) capable of high Isp thrust have been proposed. NTR employs heat produced by fission reaction to heat and therefore accelerate hydrogen which is then forced through a rocket nozzle providing thrust. Fuel element temperatures are very high (up to 3000K) and hydrogen is highly reactive with most materials at high temperatures. Data covering the effects of high temperature hydrogen exposure on fuel elements is limited. The primary concern is the mechanical failure of fuel elements which employ high-melting-point metals, ceramics or a combination (cermet) as a structural matrix into which the nuclear fuel is distributed. It is not necessary to include fissile material in test samples intended to explore high temperature hydrogen exposure of the structural support matrices. A small-scale test bed designed to heat fuel element samples via non-contact RF heating and expose samples to hydrogen is being developed to assist in optimal material and manufacturing process selection without employing fissile material. This paper details the test bed design and results of testing conducted to date.

  3. Local fallout from nuclear test detonations. Volume 2. Compilation of fallout patterns and related test data. Supplement. Foreign nuclear tests. Sanitized

    Energy Technology Data Exchange (ETDEWEB)

    Morgenthau, M.; Showers, R.L.

    1964-10-01

    The available fallout patterns and related test data for nuclear weapon tests conducted by the United Kingdom, the Republic of France, and the Union of Soviet Socialist Republics, are included in this supplement to NDL-TR-34. The related test data for the British and French tests include: date and time of detonation, location of test site, total yield, fission yield, type of burst and placement, height of burst, cloud-top and -bottom heights, crater data, and wind information up to nuclear cloud-top height. No fallout patterns are available for any of the Soviet detonations. The list of Soviet detonations, which is as comprehensive as possible, contains the chronological order of the detonations, date, yield, type of burst and location of test site.

  4. Testing of mobile surveillance robot at a nuclear power plant

    International Nuclear Information System (INIS)

    In-plant testing of a mobile surveillance robot (SURBOT) was performed at the Browns Ferry Nuclear Plant by TVA personnel. The results verified that SURBOT can be used for remote surveillance in 54 separate controlled radiation rooms at the plant. High-quality color video, audio, and other data are collected, digitized by an on-board computer, and transmitted through a cable to the control console for real-time display and videotaping. TVA projects that the use of SURBOT for surveillance during plant operation will produce annual savings of about 100 person-rem radiation exposure and $200,000 in operating costs. Based on the successful results of this program, REMOTEC is now commercializing the SURBOT technology on both wheeled and tracked mobile robots for use in nuclear power plants and other hazardous environments

  5. Nuclear thermal rocket nozzle testing and evaluation program

    International Nuclear Information System (INIS)

    Performance characteristics of the Nuclear Thermal Rocket can be enhanced through the use of unconventional nozzles as part of the propulsion system. In this report, the Nuclear Thermal Rocket nozzle testing and evaluation program being conducted at the NASA Lewis Research Center is outlined and the advantages of a plug nozzle are described. A facility description, experimental designs and schematics are given. Results of pretest performance analyses show that high nozzle performance can be attained despite substantial nozzle length reduction through the use of plug nozzles as compared to a convergent-divergent nozzle. Pretest measurement uncertainty analyses indicate that specific impulse values are expected to be within plus or minus 1.17%

  6. Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

    2013-10-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

  7. Azimuthal Anisotropies as Stringent Test for Nuclear Transport Models

    CERN Document Server

    Crochet, Philippe; Donà, R

    1997-01-01

    Azimuthal distributions of charged particles and intermediate mass fragments emitted in Au+Au collisions at 600AMeV have been measured using the FOPI facility at GSI-Darmstadt. Data show a strong increase of the in-plane azimuthal anisotropy ratio with the charge of the detected fragment. Intermediate mass fragments are found to exhibit a strong momentum-space alignment with respect of the reaction plane. The experimental results are presented as a function of the polar center-of-mass angle and over a broad range of impact parameters. They are compared to the predictions of the Isospin Quantum Molecular Dynamics model using three different parametrisations of the equation of state. We show that such highly accurate data provide stringent test for microscopic transport models and can potentially constrain separately the stiffness of the nuclear equation of state and the momentum dependence of the nuclear interaction.

  8. Safety Tests of Concrete Storage Cask for Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    In preparation for the timely installation of interim storage facility for spent nuclear fuel (SF), KORAD is developing domestic models of SF storage systems and the concrete storage cask is one of them. A concrete cask consists of a metallic canister which confines SF with welded closure and a concrete overpack which provides radiation shielding and physical protection to the canister. The safety requirements for a SF storage cask is well established in US and summarized in regulatory guides such as NUREG-1536. KAERI has been performing tests of the concrete cask to demonstrate its safety and compliance to the regulatory requirements with high priority stipulated in NUREG-1536. The test program includes the structural performance tests under tip-over and earthquake and decay heat removal test under normal, off-normal and accident conditions. In this paper, brief introduction to the structural tests and their results are provided. Safety tests to demonstrate the safety of KORAD21C concrete storage cask were successfully performed. The structural integrity during tip-over and earthquake were demonstrated with scale model tests and the results are analyzed in comparison with safety analysis results

  9. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

  10. Development and testing of restraints for nuclear piping systems

    International Nuclear Information System (INIS)

    As an alternative to current practice of pipe restraint within nuclear power plants it has been proposed to adopt restraints capable of dissipating energy in the piping system. The specific mode of energy dissipation focused upon in these studies is the plastic yielding of steels utilizing relative movement between the pipe and the base of the restraint, a general mechanism which has been proven as reliable in several allied studies. This report discusses the testing of examples of two energy-absorbing devices, the results of this testing and the conclusions drawn. This study concentrated on the specific relevant performance characteristics of hysteretic behavior and degradation with use. The testing consisted of repetitive continuous loadings well into the plastic ranges of the devices in a sinusoidal or random displacement controlled mode

  11. Developing robotics for nondestructive testing in nuclear power plants

    International Nuclear Information System (INIS)

    The ability to perform remote nondestructive testing in high radiation areas is becoming increasingly attractive as a means of minimizing radiation exposure to personnel. Robots could be used in nuclear power plants where NDT technicians are currently exposed to high levels of radiation. In developing robotics technology for this purpose, several key factors must be considered: (1) End-of-arm tooling for nondestructive testing may impose unique functional requirements for maximum effectiveness. (2) Operator definition of robot movements and limits by a joystick type of control can provide a means of rapid preprogramming. (3) An all-encompassing language used for data acquisition and closed loop control can potentially offer significant advantages. In addition, consideration is being given to the use of remote miniature solid-state television cameras to guide the technician in manipulating the robotic arm, and of X-ray vision systems for remote real-time testing

  12. Dose Prediction for surface nuclear explosions: case studies for Semipalatinsk and Lop Nur tests

    International Nuclear Information System (INIS)

    Dose prediction method RAPS after surface nuclear explosion has been developed by using the empirical dose function of USA nuclear test. This method which provides us external total dose, dose rate at any distant, at any time for any yield of nuclear explosion, is useful for radiation protection in case of nuclear events such as terrorism and nuclear war. The validity of RAPS has been confirmed by application to historical surface nuclear test explosions. The first test case study which was done for the first test explosion of the former USSR at the Semipalatinsk Nuclear Test Site on August 29th 1949, shows a good agreement with luminescence dosimetry on a brick. This dose prediction method was applied nuclear tests in Lop Nur. The results indicate dangerous nuclear radiation influences including fatal risk in the wide Uygur area. (author)

  13. Head-end demonstration test for nuclear fuel reprocessing plant 'outline of the test results'

    International Nuclear Information System (INIS)

    Japan Nuclear Fuel Ltd. (JNFL) is now constructing a nuclear fuel reprocessing plant at Rokkasho-mura (which is called Rokkasho Reprocessing plant). Concerning the head-end process, which includes shearing and dissolving processes for spent fuel and rinsing processes for end-pieces of spent fuel assemblies and chopped fuel rods, a full-scale mock-up test facility was constructed in Kobe Shipyard of Mitsubishi Heavy Industries, LTD (MHI). And then, functional and performance tests were performed using a dummy fuel assembly and chopped fuel rods, from 1988 to 1993. These tests using this full-scale mock-up test facility was called head-end demonstration test (HEDT), and this paper summarizes the results of HEDT. This HEDT facility includes five components: tilting crane, shearing machine, dissolver, hull rinser and end-piece rinser. The design of these components manufactured by MHI is based on CEA/COGEMA/SGN technology. The suitability of the design, the functional reliability, the operability, the controllability and the maintenability were evaluated through functional tests such as an operation test, for example a shearing test, under cold conditions (non radioactive). It was demonstrated that the test results were satisfactory. The component performance data and our manufacturing and operation experience will be greatly useful for the final design process and the choice of operational parameters for these head-end components of the Rokkasho Reprocessing Plant. (author)

  14. External Doses of Residents near Semipalatinsk Nuclear Test Site

    OpenAIRE

    Takada, Jun; Hoshi, Masaharu; NAGATOMO, Tsuneto; Yamamoto, Masayoshi; Endo, Satoru; Takatsuji, Toshihiro; Yoshikawa, Isao; Gusev, Boris I.; Sakerbaev, Alexander K.; Tchaijunusova, Nailya J.

    1999-01-01

    Accumulated external radiation doses of residents near the Semipalatinsk nuclear test site of the former USSR are presented as a results of study by the thermoluminescence technique for bricks sampled at several settlements in 1995 and 1996. The external doses that we evaluated from exposed bricks were up to about 100 cGy for resident. The external doses at several points in the center of Semipalatinsk City ranged from a background level to 60 cGy, which was remarkably high compared with the ...

  15. Mortality of veteran participants in the crossroads nuclear test

    International Nuclear Information System (INIS)

    Operation CROSSROADS, conducted at Bikini Atoll in 1946, was the first post World War II test of nuclear weapons. Mortality experience of 40,000 military veteran participants in CROSSROADS was compared to that of a similar cohort of nonparticipating veterans. All-cause mortality of the participants was slightly increased over nonparticipants by 5% (p < .001). Smaller increases in participant mortality for all malignancies (1.4%, p = 0.26) or leukemia (2.0%, p = 0.9) were not statistically significant. These results do not support a hypothesis that radiation had increased participant cancer mortality over that of nonparticipants. 8 refs

  16. Mortality of veteran participants in the CROSSROADS nuclear test.

    Science.gov (United States)

    Johnson, J C; Thaul, S; Page, W F; Crawford, H

    1997-07-01

    Operation CROSSROADS, conducted at Bikini Atoll in 1946, was the first post World War II test of nuclear weapons. Mortality experience of 40,000 military veteran participants in CROSSROADS was compared to that of a similar cohort of nonparticipating veterans. All-cause mortality of the participants was slightly increased over nonparticipants by 5% (p < .001). Smaller increases in participant mortality for all malignancies (1.4%, p = 0.26) or leukemia (2.0%, p = 0.9) were not statistically significant. These results do not support a hypothesis that radiation had increased participant cancer mortality over that of nonparticipants. PMID:9199228

  17. Contaminant Boundary at the Faultless Underground Nuclear Test

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP) have reached agreement on a corrective action strategy applicable to address the extent and potential impact of radionuclide contamination of groundwater at underground nuclear test locations. This strategy is described in detail in the Federal Facility Agreement and Consent Order (FFACO, 2000). As part of the corrective action strategy, the nuclear detonations that occurred underground were identified as geographically distinct corrective action units (CAUs). The strategic objective for each CAU is to estimate over a 1,000-yr time period, with uncertainty quantified, the three-dimensional extent of groundwater contamination that would be considered unsafe for domestic and municipal use. Two types of boundaries (contaminant and compliance) are discussed in the FFACO that will map the three-dimensional extent of radionuclide contamination. The contaminant boundary will identify the region wi th 95 percent certainty that contaminants do not exist above a threshold value. It will be prepared by the DOE and presented to NDEP. The compliance boundary will be produced as a result of negotiation between the DOE and NDEP, and can be coincident with, or differ from, the contaminant boundary. Two different thresholds are considered for the contaminant boundary. One is based on the enforceable National Primary Drinking Water Regulations for radionuclides, which were developed as a requirement of the Safe Drinking Water Act. The other is a risk-based threshold considering applicable lifetime excess cancer-risk-based criteria The contaminant boundary for the Faultless underground nuclear test at the Central Nevada Test Area (CNTA) is calculated using a newly developed groundwater flow and radionuclide transport model that incorporates aspects of both the original three-dimensional model (Pohlmann et al., 1999) and the two-dimensional model developed for the Faultless data decision

  18. Application of the isotopic ratio based method for discrimination between nuclear tests and nuclear reactors on various data sets

    International Nuclear Information System (INIS)

    The monitoring of atmospheric radioxenon is a crucial element in the verification of the comprehensive nuclear-test-ban treaty (CTBT). In order to discriminate between legitimate nuclear reactor emissions and nuclear explosions, the isotopic activity ratios can be used. Various data sets are used to demonstrate the discrimination capability of the isotopic radio method. These include daily and annual emission reports from nuclear power plants and atmospheric observations at various sites. Five air samples are of special interest. They were measured a few days after the North Korean nuclear test in October 2006

  19. Generation of aerosols for filter efficiency testing in nuclear installations

    International Nuclear Information System (INIS)

    The purpose of the Research Contract No. 1815 was to develop a new method of sodium chloride aerosol generation for filter efficiency testing in nuclear installations. The first phase of the study was devoted to the development of a suitable aerosol generator. The first NaCl aerosol generator enabled determination of the influence various parameters like nozzle diameter, air flow rate, NaCl concentration in solution, solution temperature, etc., on the generation capacity and aerosol characteristics. The drawbacks of this generator were removed by modifying the design. Sodium chloride aerosol concentration was measured by means of a portable sodium flame photometer, and the particle size distribution was determined by a six-stage Andersen cascade impactor. For particle shape analysis electron microscopy was used. By using the aerosols generated the efficiency of air filters was tested. The results showed that the optimum parameters for atomization of 24NaCl solution are: Nozzle diameter 0.5x10-3m; compressed air pressure 196.132kPa; air flow rate 6.1x10-5m3/s. Under these conditions test aerosols of 0.335x10-6m mass median diameter were obtained with a geometrical standard deviation, sigma=2.04. Preliminary high efficiency particulate air filter tests with the above 24NaCl aerosols showed the minimum filter penetration of the order of 5x10-5% with a relative standard deviation not exceeding 15%. This showed that the 24NaCl aerosol generated from liquid phase can be successfully used for filter testing in nuclear installations

  20. EDF experimental test facilities for main components of nuclear power stations

    International Nuclear Information System (INIS)

    Several facilities essentially designed to test nuclear power plant equipment, whose purpose is to improve the availability of nuclear power stations, are described: test loop for water reactor primary pumps, test rig for separators, wet steam test turbine, test loop for Super-Phenix pumps

  1. Y-12 defense programs. Nuclear Packaging Systems testing capabilities

    International Nuclear Information System (INIS)

    The Nuclear Packaging Systems (NPS) Department can manage/accomplish any packaging task. The NPS organization is responsible for managing the design, testing, certification, procurement, operation, refurbishment, maintenance, and disposal of packaging used to transport radioactive materials, other hazardous materials, and general cargoes on public roads and within the Oak Ridge Y-12 Plant. Additionally, the NPS Department has developed a Quality Assurance plan for all packaging, design and procurement of nonweapon shipping containers for radioactive materials, and design and procurement of performance-oriented packaging for hazardous materials. Further, the NPS Department is responsible for preparation and submittal of Safety Analysis Reports for Packaging (SARP). The NPS Department coordinates shipping container procurement and safety certification activities that have lead-times of up to two years. A Packaging Testing Capabilities Table at the Oak Ridge complex is included as a table

  2. Small Punch Tests applied to the nuclear industry

    International Nuclear Information System (INIS)

    The interest on miniaturized specimen techniques for the characterization of the mechanical behavior of materials was strongly motivated in the early eighties by the different programs associated with the development of fusion reactor technology. The importance of such developments is obvious in the case of the nuclear industry where the limited space available, the presence of fluence gradients in large specimens, the concern about gamma heating and dose to personnel in post-irradiation testing have all been motivations for reducing specimen size. Testing of miniature specimen includes a wide spectrum of techniques such as tensile, instrumented micro-hardness, small punch, bend, fracture, impact and fatigue. Small Punch Testing (SPT) techniques use a spherical penetrator which deforms to failure a miniature disc shaped flat specimen (typically, 3-10 mm in diameter and 0.25-0.50 mm in thickness) supported on its outer rim. Analysis of load-displacement data recorded along the test is performed for the determination of the property of interest. The present work focuses on the characterization of the elastoplastic response of pure Al, ADN 420 structural steel and AISI 304L using SPT and its correlation with the associated standard uniaxial testing behavior. In addition, the sensitivity of the technique to the specific material under study and to different experimental parameters, i.e. specimen diameter and thickness, clearance or clamping force and friction between disc and dies have been assessed both experimentally and by performing simulations using the finite element method (author)

  3. A Preliminary study on attitudes toward nuclear weapons and nuclear tests of the residents of Kurchatov, Kazakhstan

    OpenAIRE

    Matsuo, Masatsugu; Bektorov, Yerzhan; Muldagaliyev, Talgat; Apsalikov, Kazbek; Hirabayashi, Kyoko; Kawano, Noriyuki

    2006-01-01

    The town of Kurchatov was a secret city newly built in the Semipalatinsk nuclear test site as the headquarters of the nuclear tests. The present paper is a pilot study, first, to explore how the current Kurchatov residents think and feel about nuclear weapons and nuclear tests, and secondly, to compare the results of the survey with those of the similar survey near Semipalatinsk. Though the present study is based upon a small and limited survey conducted in the city, it is hoped that it will ...

  4. Fast recovery strain measurements in a nuclear test environment

    International Nuclear Information System (INIS)

    The recovery of early-time (50 μs or less) strain gage data on structural response experiments in underground nuclear tests has been a continuing problem for experimenters at the Nevada Test Site. Strain measurement is one of the primary techniques used to obtain experimental data for model verification and correlation with predicted effects. Peak strains generally occur within 50 to 100 μs of the radiation exposure. Associated with the exposure is an intense electromagnetic impulse that produces potentials of kilovolts and currents of kiloamperes on the experimental structures. For successful operation, the transducer and associated recording system must recover from the initial noise overload and accurately track the strain response within about 50 μs of the nuclear detonation. A gaging and fielding technique and a recording system design that together accomplish these objectives are described. Areas discussed include: (1) noise source model; (2) experimental cassette design, gage application, grounding, and shielding; (3) cable design and shielding between gage and recorder; (4) recorder design including signal conditioner/amplifier, digital encoder, buffer memory, and uphole data transmission; and (5) samples of experimental data

  5. Qualification tests for shift personnel in nuclear power plants

    International Nuclear Information System (INIS)

    The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors. (orig.)

  6. Ionizing radiations, underground world and nuclear tests in Algeria

    Science.gov (United States)

    Chama, Allel

    2010-05-01

    Today, the exposure to ionizing radiations, is still a real great physical hazard in the world at various levels until the nuclear tests which led to a rich and lawful debate, and needs the installation of preventive rules through technical and medical aspects during the use of the radioactive sources, (theradioprotection). Concerning the occupational health, the pathology of the ionizing radiations is repaired under occupational disease. Our interest is to highlight this physical hazard, which represents an important chapter of the occupational pathology in its effects and prevention of the workers exposed in Algeria. The second aim of the paper is to highlight the historical aspect of the risk of ionizing radiations and consequences causes by the French nuclear tests in In Eker (underground galleries of the mountain of Hoggar in the south of Algeria in 1961), whose effects present a great damage on the health of the Algerian captive, and "workers", indigenous population and environment until now. This event deserves its place as much as that of Hiroshima and Nagasaki (1945).

  7. Bikini Atoll coral biodiversity resilience five decades after nuclear testing

    International Nuclear Information System (INIS)

    Five decades after a series of nuclear tests began, we provide evidence that 70% of the Bikini Atoll zooxanthellate coral assemblage is resilient to large-scale anthropogenic disturbance. Species composition in 2002 was assessed and compared to that seen prior to nuclear testing. A total of 183 scleractinian coral species was recorded, compared to 126 species recorded in the previous study (excluding synonomies, 148 including synonomies). We found that 42 coral species may be locally extinct at Bikini. Fourteen of these losses may be pseudo-losses due to inconsistent taxonomy between the two studies or insufficient sampling in the second study, however 28 species appear to represent genuine losses. Of these losses, 16 species are obligate lagoonal specialists and 12 have wider habitat compatibility. Twelve species are recorded from Bikini for the first time. We suggest the highly diverse Rongelap Atoll to the east of Bikini may have contributed larval propagules to facilitate the partial resilience of coral biodiversity in the absence of additional anthropogenic threats

  8. Activities related to ''nuclear model parameter testing for nuclear data evaluation'' (Reference Input Parameter Library: Phase II) at CNDC

    International Nuclear Information System (INIS)

    The objectives of the RIPL CRP Phase II are to test thoroughly all segments of the Starter File of the Reference Input Parameter Library, focusing on optical model parameters and nuclear level density parameters. The nuclear level density calculations for 303 nuclei with the two recommended parameter sets have been performed. 88 sets of optical potential parameters are prepared for RIPL-2. A nuclear model code UNF is being prepared at CNDC for the physical testing of RIPL. (author)

  9. Microquake activity associated with underground nuclear testing at the Nevada Test Site

    International Nuclear Information System (INIS)

    In the fall of 1976, the Los Alamos Close-In Seismic Network was added to the existing strong motion net deployed around each nuclear test conducted by Los Alamos. Six to ten stations, including both accelerometers and seismometers, are installed within a two-DOB (depth of burial) circle around SGZ (surface ground zero) and operated until the major portion of the microquake activity ceases, usually within 48 hours. Epicentral locations are determined and local magnitudes are calculated from event durations. Four primary conclusions have been reached on the basis of the data analyzed to date: (1) major faults bounding the immediate site of a nuclear test confine the observed microquake activity to the structural block in which the test is conducted; (2) microquake epicenters are generally distributed around the cavity created by the nuclear test with the peak occurrence generally occurring about three cavity radii away from the working point; (3) magnitudes of locatable microquakes apparently distribute randomly over the entire region of activity; and (4) the microquake activity as a function of time appears to be controlled by the collapse phenomenology

  10. Ionospheric Effects of Underground Nuclear Explosions

    Science.gov (United States)

    Park, J.; von Frese, R. R.; G-Brzezinska, D. A.; Morton, Y.

    2010-12-01

    Telemetry from the Russian INTERCOSMOS 24 satellite recorded ELF and VLF electromagnetic disturbances in the outer ionosphere from an underground nuclear explosion that was detonated at Novaya Zemlya Island on 24 October 1994. The IC24 satellite observations were obtained at about 900 km altitude within a few degrees of ground zero. The disturbances were interpreted for magnetohydrodynamic excitation of the ionosphere’s E layer by the acoustic wave. Electrons are accelerated along the magnetic force lines to amplify longitudinal currents and magnetic disturbances that may be measured by magnetometers at ground-based observatories and on-board satellites. The underground nuclear test near P’unggye, North Korea on 25 May 2009 provides a further significant opportunity for studying the utility of ionospheric disturbances for characterizing ground zero. Of the seismic, infrasound, hydroacoustic, and radionuclide detection elements of the International Monitoring System (IMS) established by the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO), only the first two elements detected this event. However, the event also appears to have been recorded as a direct traveling ionospheric disturbance (TID) in the slant total electron content (TEC) observations derived from a network of the Global Navigation Satellite System (GNSS) measurements. The TID was observed to distances of at least 600 km from the explosion site propagating with a speed of about 281m/s. Thus, the global distributions and temporal variations of the TEC, may provide important information to help detect and characterize clandestine underground nuclear explosions.

  11. An Enhancement of Visual Test Performance for Nuclear Fuel Assembly

    International Nuclear Information System (INIS)

    In the overhaul period of the nuclear power plant, integrity of the neutron-irradiated fuel assembly is evaluated. Nuclear regulations require that nuclear power plants meet the design, operation, and inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B and PV). Section XI of the ASME B and PV Code provides the specific requirements for inspecting the systems, structures, and components; Section V of the ASME Code provides requirements for inspection methods, including volumetric (e.g., ultrasonic testing), surface (e.g., eddy current testing), and visual testing (VT). Visual testing of neutron irradiated fuel assembly is conducted generally for a variety of purposes, for example to detect discontinuities and imperfections on the surface of fuel rods, to detect evidence of leakage from end-cap welds, and to determine the general mechanical and structural condition of one. VT is performed remotely using video camera. As the neutron-irradiated fuel assembly is a high dose-rate gamma-ray source, approximately a few kGy, radiation hardened underwater camera is used in the VT of the fuel assembly. Utilities today follow the EPRI guidelines for VT-1 tests on nuclear components (BWR Vessel and Internals Project-3 1995). The VT-1 guidelines specify which areas around a weld should be examined, how to measure the sizes of indications found, and how to test the resolving power of the visual equipment used for the test. The EPRI guidelines use two 12μm (0.0005-in.) wires or notches as a resolution calibration standard. According to the EPRI guidelines (BWRVIP-03 1995), the camera systems employed were marginally able to detect the 0.0005-inch (12-μm) diameter wire on a steel background. In the some future, it is required that the VT of nuclear fuel assembly follows the EPRI VT-1 guideline. In order to meet the VT-1 guideline, any system used in VT (ranging from the naked eye to a digital closed-circuit TV system

  12. An Enhancement of Visual Test Performance for Nuclear Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jai Wan; Choi, Young Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Shin, Jung Cheol [Korea Nuclear Fuel, Daejeon (Korea, Republic of)

    2009-05-15

    In the overhaul period of the nuclear power plant, integrity of the neutron-irradiated fuel assembly is evaluated. Nuclear regulations require that nuclear power plants meet the design, operation, and inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B and PV). Section XI of the ASME B and PV Code provides the specific requirements for inspecting the systems, structures, and components; Section V of the ASME Code provides requirements for inspection methods, including volumetric (e.g., ultrasonic testing), surface (e.g., eddy current testing), and visual testing (VT). Visual testing of neutron irradiated fuel assembly is conducted generally for a variety of purposes, for example to detect discontinuities and imperfections on the surface of fuel rods, to detect evidence of leakage from end-cap welds, and to determine the general mechanical and structural condition of one. VT is performed remotely using video camera. As the neutron-irradiated fuel assembly is a high dose-rate gamma-ray source, approximately a few kGy, radiation hardened underwater camera is used in the VT of the fuel assembly. Utilities today follow the EPRI guidelines for VT-1 tests on nuclear components (BWR Vessel and Internals Project-3 1995). The VT-1 guidelines specify which areas around a weld should be examined, how to measure the sizes of indications found, and how to test the resolving power of the visual equipment used for the test. The EPRI guidelines use two 12{mu}m (0.0005-in.) wires or notches as a resolution calibration standard. According to the EPRI guidelines (BWRVIP-03 1995), the camera systems employed were marginally able to detect the 0.0005-inch (12-{mu}m) diameter wire on a steel background. In the some future, it is required that the VT of nuclear fuel assembly follows the EPRI VT-1 guideline. In order to meet the VT-1 guideline, any system used in VT (ranging from the naked eye to a digital closed-circuit TV

  13. An Evaluation of North Korea’s Nuclear Test by Belbasi Nuclear Tests Monitoring Center-KOERI

    Science.gov (United States)

    Necmioglu, O.; Meral Ozel, N.; Semin, K.

    2009-12-01

    Bogazici University and Kandilli Observatory and Earthquake Research Institute (KOERI) is acting as the Turkish National Data Center (NDC) and responsible for the operation of the International Monitoring System (IMS) Primary Seismic Station (PS-43) under Belbasi Nuclear Tests Monitoring Center for the verification of compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT) since February 2000. The NDC is responsible for operating two arrays which are part of the IMS, as well as for transmitting data from these stations to the International Data Centre (IDC) in Vienna. The Belbasi array was established in 1951, as a four-element (Benioff 1051) seismic array as part of the United States Atomic Energy Detection System (USAEDS). Turkish General Staff (TGS) and U.S. Air Force Technical Application Center (AFTAC) under the Defense and Economic Cooperation Agreement (DECA) jointly operated this short period array. The station was upgraded and several seismometers were added to array during 1951 and 1994 and the station code was changed from BSRS (Belbasi Seismic Research Station) to BRTR-PS43 later on. PS-43 is composed of two sub-arrays (Ankara and Keskin): the medium-period array with a ~40 km radius located in Ankara and the short-period array with a ~3 km radius located in Keskin. Each array has a broadband element located at the middle of the circular geometry. Short period instruments are installed at depth 30 meters from the surface while medium and broadband instruments are installed at depth 60 meters from surface. On 25 May 2009, The Democratic People’s Republic of Korea (DPRK) claimed that it had conducted a nuclear test. Corresponding seismic event was recorded by IMS and IDC released first automatic estimation of time (00:54:43 GMT), location (41.2896°N and 129.0480°E) and the magnitude (4.52 mb) of the event in less than two hours time (USGS: 00:54:43 GMT; 41.306°N, 129.029°E; 4.7 mb) During our preliminary analysis of the 25th May 2009 DPRK

  14. In situ testing of motor-operated valves in nuclear power plants

    International Nuclear Information System (INIS)

    This paper presents a perspective of the status of in situ testing of motor operated valves in nuclear power plants. The objectives of in situ testing are discussed. A short history of in situ testing of motor-operated valves in nuclear plant applications is offered. Recent developments regarding in situ testing are discussed followed by a perspective on needed research and development

  15. Nuclear Performance Analyses for HCPB Test Blanket Modules in ITER

    International Nuclear Information System (INIS)

    calculations were performed for assessing the nuclear performance of HCPB blanket test modules in terms of the Tritium generation, the nuclear heating and the radiation shielding. The shielding calculations include the evaluation of the transmitted neutron radiation and the gamma dose rate around the port after shutdown. Three-dimensional activation and afterheat calculations were performed for the PI variant of the HCPB TBM to provide the data required for quality assured safety analyses. (author)

  16. Specification and acceptance testing of nuclear medicine equipment

    International Nuclear Information System (INIS)

    The purchase of nuclear medicine equipment is of prime importance in the operation of a clinical service. Failure to properly evaluate the potential uses of the instrumentation and the various operational characteristics of the equipment can often result in the purchase of inappropriate or inferior instruments. The magnitude of the purchase in terms of time and financial investments make it imperative that the purchase be approached in a systematic manner. Consideration of both the intended clinical functions and personnel requirements is important. It is necessary also to evaluate the ability of the equipment vendor to support the instrumentation after the purchase has been completed and the equipment installed in the clinical site. The desired specifications of the instrument characteristics should be stated in terms that can be verified by acceptance testing. The complexity of modern instrumentation and the sensitivity of it to the environment require the buyer to take into account the potential problems of controlling the temperature, humidity, and electrical power of the installation site. If properly and systematically approached, the purchase of new nuclear medicine instrumentation can result in the acquisition of a powerful diagnostic tool which will have a useful lifetime of many years. If not so approached, it may result in the expenditure of a large amount of money and personnel time without the concomitant return in useful clinical service. (author)

  17. Thermal Simulator Development: Non-Nuclear Testing of Space Fission Systems

    Science.gov (United States)

    Bragg-Sitton, Shannon M.; Dickens, Ricky E.

    2006-01-01

    Non-nuclear testing can be a valuable tool in the development of a space nuclear power system. At the NASA MSFC Early Flight Fission Test Facility (EFF-TF), highly designed electric heaters are used to simulate the heat from nuclear fuel to test space fission power and propulsion systems. To allow early utilization, nuclear system designs must be relatively simple, easy to fabricate, and easy to test using non-nuclear heaters to closely mimic heat from fission. In this test strategy, highly designed electric heaters are used to simulate the heat from nuclear fuel, allowing one to develop a significant understanding of individual components and integrated system operation without the cost, time and safety concerns associated with nuclear testing.

  18. Nuclear weapons and the Arab-Israeli conflict

    International Nuclear Information System (INIS)

    The implications of the clandestine Israeli nuclear arsenal for the conflict in the Middle East are studied in the light of emerging Arab reactions to it. The opportunities for European influence on the policy and programmes of this threshold state are described

  19. Sensitive change detection for remote sensing monitoring of nuclear treaties

    DEFF Research Database (Denmark)

    Canty, Morton J.; Nielsen, Allan Aasbjerg; Schlittenhardt, Jörg

    2005-01-01

    change is a commonplace application in remote sensing, the detection of anthropogenic changes associated with nuclear activities, whether declared or clandestine, presents a difficult challenge. It is necessary to discriminate subtle, often weak signals of interest on a background of irrelevant or...

  20. Rehabilitation of former nuclear test sites in Australia

    International Nuclear Information System (INIS)

    A range of options with indicative cost estimates and timescale has been defined for clean-up of the former British nuclear test sites at Maralinga and Emu in South Australia. The situation at the former test sites on the Monte Bello Islands has been reported separately. The predominant contributor to potential radiation dose at the test sites is residual plutonium contamination of soil which may be incorporated into the body through inhalation of resuspended dust. Acceptable levels of radioactive soil contamination based upon organ doses from incorporated plutonium and the associated health detriment are proposed by the Technical Assessment Group for a series of land-use options ranging from fully unrestricted habitation by Aboriginals including the case of high dependence on local plants and animals for food: to casual access by Aboriginals assuming retained or, if necessary, extended fences. The area of land affected and the quantity of soil and other material with more than the proposed limit of contamination as well as a range of remedial measures for reduction of the contamination to a level acceptable for each of the land-use options has been assessed and methods proposed for safe disposal of the contaminated materials. The associated costs of these remedial measures and disposal methods have also been estimated. 28 refs., 71 tabs., 45 figs

  1. Devices and Instrumentations for Nuclear Fuel Irradiation Tests in HANARO

    International Nuclear Information System (INIS)

    HANARO(High flux Advanced Neutron Application ReactOr), one of the multipurpose research reactors in the world, has a maximum thermal power of 30MW. HANARO has been operated and the functions of its systems have been improved continuously since its first criticality in February 1995, and it is now being successfully utilized in such areas as fuel and materials irradiation tests, neutron beam research, radioisotopes production, neutron activation analysis, and neutron transmutation doping, etc. Experimental facilities, such as capsules, FTL including control system and others, have been developed and installed in field of irradiation tests since the beginning of the reactor's operation, and continued efforts to develop more equipment and to enhance an irradiation technology are in progress. The support of the government for HANARO users has promoted new researches in a wide range of neutron application, which is demonstrated by the high growth record of HANARO's utilization every year. In this paper, experimental equipment for irradiation tests of nuclear fuels and instrumentation to measure some characteristics of fuels during irradiation in HANARO are described

  2. Acceptance test of graphite components in nuclear reactor

    International Nuclear Information System (INIS)

    The HTTR is the first high temperature gas-cooled reactor in Japan. It is a test reactor with thermal power of 30 MW and coolant outlet temperature of 950degC at maximum. To achieve high temperature coolant core internals were made of graphite and carbon materials due to their excellent thermal resistivity. After fabrication of graphite and carbon components at works they were installed in the HTTR, and now it is in the power up testing stage. Concerning the inspection standard of the graphite and carbon components, nondomestic standard exists as main components in the nuclear reactor. It is necessary, therefore, to prescribe the inspection standards for the HTTR graphite components. Many research and developments in relation to the inspection standard, e.g. in the research field of nondestructive examination of the graphite material, had been performed, and then the JAERI established the inspection standard. The acceptance test of the graphite and carbon components was carried out based on the inspection standard. This paper prescribes the outline of the established inspection standard. (author)

  3. Techniques of the snubber testing in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Soon Sin; Kim, Byung Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-05-01

    The performance of PSI/ISI is one of the important inspections which improve the safety, reliability and operability of nuclear power plant. Therefore, KAERI has performed the inspections for the safety-related piping systems, pressure vessel and support components of NPP by the NDT methods in accordance with the related technical codes and standards. ASME Sec.XI of 1989 requires to perform the visual inspection and functional test of snubbers in accordance with ASME/ANSI OM-Part 4 additionally. Especially, the inspection and functional test of heavy duty hydraulic snubbers attached to the steam generator and RC pump have also been added. The main role of snubbers protects the piping system and pressure vessel from the transient events such as water hammer and earthquake during operation. Throughout the analysis of the status of snubbers in NPP, the snubber failure cases in domestic and foreign countries, the requirements and technical standards of the inspection and test, problems of snubbers in NPP, and snubber reduction program, this report requires to follow the technical codes and standards for the inspection and functional test of snubbers now being insufficient in Korean NPP. As a following action, the safety verification analysis for the reliability of piping systems and components of NPP due to snubber failure causes will be studied, and also the snubber reduction program of NPP will simplify the control and maintenance of the expensive snubbers. The objective of this report is to provide the problems of snubber in Korean NPP and contribute to the integrity assurance of the piping systems and components by the inspection and test of snubbers. 17 figs., 9 tabs., 19 refs. (Author).

  4. Very high temperature measurements: Applications to nuclear reactor safety tests

    International Nuclear Information System (INIS)

    This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

  5. Worldwide fallout of plutonium from nuclear weapons tests

    International Nuclear Information System (INIS)

    Measurements of 238Pu and /sup 239,240/Pu fallout from nuclear weapons tests and the SNAP-9A navigational satellite burnup are presented for the years through 1980. Data abstracted from the literature were taken from the stratosphere, atmosphere, and from deposition and surface soil. Over 7300 data entries are included in the 23 tables. The tables are sorted by medium (stratosphere, atmosphere, and deposition near the surface and soil, nuclide, hemisphere, and longitude going from west to east, and are arranged in chronological order. Latitudes are also provided. Fallout levels in SI units (becquerels), calculated from the original readings, and the references from which the original data were taken are given in the report. The appendix is a map showing the various sites from which data were obtained

  6. Procedural development for nuclear waste canister impact testing

    International Nuclear Information System (INIS)

    Double containment requirements for transporting nuclear waste in glass form are costly and may not be necessary for some waste forms. To allow single containment, a procedure for examining particle size distribution and the amount of respirable particles generated under accident conditions was needed. A statistically designed experiment was conducted to examine the effects of glass temperature, fill rate and canister drop orientation upon the amount of sub-ten micron particles generated under simulated accident conditions. Measuring such small particles is somewhat inaccurate because of material loss in handling. By assuming a lognormal particle size distribution, the amount of sub-ten micron particles was estimated from the results for the larger measurable particles. Analyses revealed no temperature or fill rate effect but indicated that the amount of respirable particles is affected by drop orientation. This led to identification of a worst case drop orientation to be used in qualification testing. 4 refs., 2 figs

  7. Rockbursts as opportunities for the concealment of nuclear tests?

    Energy Technology Data Exchange (ETDEWEB)

    Heuze, F.E.

    1994-01-01

    Based on a review of the engineering and scientific literature from 1979 to 1993 concerning mine rockbursts, it is concluded that the hiding of nuclear tests in rockbursts is a highly improbable scenario. This is due to the lack of ability for anyone to accurately predict the time and location of occurrence of natural rockbursts, in spite of active research on the subject. However, such an evasion scheme is not impossible. A contrived rockburst possibly could be made to happen in a somewhat ``controlled`` fashion. This rather far-fetched scenario is outlined in the discussion. Such an event most likely would involve serious damage to the underground, and would be unlikely to be repeated frequently at any given site. Moreover, it would be extremely difficult to control its seismic magnitude.

  8. Delayed consequences of nuclear tests on Semipalatinsk site

    International Nuclear Information System (INIS)

    Data of delayed radiation influence on body of the man and animals are sited. Long-term observations of residents in the vicinity to the nuclear site show two-phase character of cardiovascular and the nervous systems pathological disturbances, which on 10 years outstripping the natural age shifts, e. g. premature growing old. One of the dangerous radiation injuries is development of malignant neoplasms. In comparing with 1957 now the mortality from cancer of different localization with Semipalatinsk city inhabitants grows up in to 2.5-3 times. Observations reveal that oncological illness and mortality from cancer sharply increase on 4-t h, 15-t h and 23-27-t h years after the tests realization. Average annual growth rate of mortality from malignant neoplasms of population irradiated in the result of nuclear test is higher in 40 %, than in control groups. Quantity of ills with leukemia increases in to 7 times in comparing with 1985. It is established that frequency chromosomal aberrations with indigenous inhabitants in 4-5 times higher than in the control groups. Principal reasons of the delayed radiation effects are as follows: significant lowering of immune system activity, cytogenetic disturbances, lowering of body radioresistance, metabolism disturbances and systems of adaptation regulation. Hemic examination of animals peripheral blood does not revealed changes typical to radiation pathology. Rate between increase of natural immunity and density of territory radiation contamination was established. So, rate of immunosuppression in zone of emergency risk made up 55 %, maximal - 25 %, and increased - 15 % in comparing with animals in zone of minimal radiation risk. The most distributed diseases with animal in this region is crystalline lens clouding

  9. SFC/SFBMN guidelines update for nuclear cardiology procedures: stress testing in adults and children

    International Nuclear Information System (INIS)

    The guidelines update for nuclear cardiology procedures are studied in this article. We find the minimum technique conditions for the stress testing practice, the recommendations for the different ischemia activation tests, the choice of the stress test. (N.C.)

  10. Ground Test Facility for Propulsion and Power Modes of Nuclear Engine Operation

    International Nuclear Information System (INIS)

    Existing DOE Ground Test Facilities have not been used to support nuclear propulsion testing since the Rover/NERVA programs of the 1960's. Unlike the Rover/NERVA programs, DOE Ground Test facilities for space exploration enabling nuclear technologies can no longer be vented to the open atmosphere. The optimal selection of DOE facilities and accompanying modifications for confinement and treatment of exhaust gases will permit the safe testing of NASA Nuclear Propulsion and Power devices involving variable size and source nuclear engines for NASA Jupiter Icy Moon Orbiter (JIMO) and Commercial Space Exploration Missions with minimal cost, schedule and environmental impact. NASA site selection criteria and testing requirements are presented

  11. Recurrent ultrasonic inspections in nuclear power plants. Application of optimized test procedures

    International Nuclear Information System (INIS)

    Specifications for recurrent ultrasonic inspections of nuclear facilities are contained in the KTA nuclear rules and regulations. Often, optimised test methods must be applied, e.g. because of damage occurring during operation. Such techniques are used especially in tests whose results can be applied to other, similar test objects. Simulations using CIVA software make it possible to test and simulate possible optimum ultrasonic test parameters for complex test pieces already in the planning stage.

  12. Experimental facility for the nuclear planetology instruments testing

    International Nuclear Information System (INIS)

    The experimental facility for testing and calibration of nuclear planetology instruments has been built in the frame of JINR and Space Research Institute (Moscow) cooperation. The Martian soil model from silicate glass with dimensions 3.82×3.21 m and total weight near 30 t has been assembled in the facility. The glass material was chosen for imitation of absolutely dry Martian regolith. The heterogeneous model has been proposed and developed to achieve the most possible similarity with Martian soil in part of the average elemental composition by adding layers of necessary materials, such as iron, aluminum, and chlorine. The presence of subsurface water ice is simulated by adding layers of polyethylene at different depths inside glass model assembly. The portable pulse neutron generator was used as a neutron source to test active neutron and gamma spectrometers. The facility is a radiation hazard area and that is why it is equipped with locking and radiation monitoring systems in accordance with national radiation safety regulations

  13. Nuclear aerosol test facility studies using plasma torch aerosol generator

    International Nuclear Information System (INIS)

    In order to study the behavior of aerosols released into the reactor containment following accidents, an experimental simulation facility, called Nuclear Aerosol Test Facility (NATF) has recently been built and commissioned in BARC. It mainly consists of a Test vessel for simulating the containment, plasma torch aerosol generator (PTAG) system for generating metal-based aerosols and aerosol monitoring instrumentation. The main component of the PTAG is a 40 kW dc plasma torch, powered by a constant current power supply, operating in a non-transferred arc mode. Optimal operating conditions of PTAG have been established. Experiments consist of injecting the aerosols of a given material for about 20 minutes into the vessel, simultaneously monitoring the concentrations at various points in the vessel. The measurements of the size distribution and mass concentrations in the vessel are carried out at periodic intervals. Various combination of experiments with different metals such as zinc, tin and manganese, under varying turbulence conditions (with and without keeping the fan continuously on) have been performed. The aerosols were generally found to be fractal aggregates with low fractal dimension (∼1.6). The mass depletion data have been subjected to theoretical analysis and validation exercises with available aerosol behavior codes. The results are further discussed. (author)

  14. Environmental tests of electric cables for nuclear power plants

    International Nuclear Information System (INIS)

    The evaluation of the materials for flame retardation of cables for nuclear power plants and the tests of their environmental resistivity are reported. Several cables to meet the severe requirements for these cables have been produced for trial, which have been subjected to the simulated environment test including Loss of Coolant Accident. The results are summarized as follows: (a) the ethylene-proylene rubber-insulated, chloroprene-sheathed cable has the sufficient properties to use in BWR containment vessels, such as radiation resistance and flame resistance. (b) It is the same in the chloroprene-sheathed cable, that has glass braids on the outermost layer and around each core, and the insulation layer of the silicone rubber electrically stable but mechanically low in radiation resistivity. (c) The flame-resistant cross-linking polyethylene-insulated, low hydrochloric acid vinyl-sheathed cable is usable near but outside BWR containment vessels. (d) The flame-resistant cross-linking polyethylene-insulated, chloroprene-sheathed cable having the insulating layer of polyethylene for each core can be used in PWR containment vessels. (e) Chloroprene and polyvinyl chloride, the flame-resistant sheath materials, deteriorate owing to heat aging alone. Only the insulating layers mainly contribute to the environmental resistivity of cables. (f) The environmental conditions are severer when heat aging is carried out prior to irradiation. The influence of dose rate is rather little. (Wakatsuki, Y.)

  15. Qualification process for ultrasonic testing in nuclear inservice inspection applications

    International Nuclear Information System (INIS)

    This report documents a project whose objective was to develop recommended requirements and processes for qualifying ultrasonic testing/inservice inspection (UT/ISI) systems for ISI of nuclear power plant components. An overall qualification process intended to achieve statistically designed performance validations including prerequisite training and other qualification recommendations is described. This report also contains recommendations for the test specimens, environment, and other conditions under which the qualification processes should be conducted. Active involvement in the ASME Section 11 Subgroup on Nondestructive Examination (SGNDE) and an Ad Hoc Task Group authorized by the SGNDE became an integral part of this task after a PNL draft document was presented in November 1984. The major areas where specific enhancements to Section 11 were recommended in this document included more stringent criteria for Level 3 qualifications, explicit recommendations for requalification, inauguration of periodic (annual) training, and recommendations for coordinating and administering the entirely new qualification process on a national (rather than local employer) basis. 23 refs., 14 figs., 2 tabs

  16. Airflow Patterns In Nuclear Workplace - Computer Simulation And Qualitative Tests

    International Nuclear Information System (INIS)

    Concentration of airborne radioactive materials inside a room can vary widely from one location to another, sometimes by orders of magnitude even for locations that are relatively close. Inappropriately placed samplers can give misleading results and. therefore, the location of air samplers is important. Proper placement of samplers cannot be determined simply by observing the position of room air supply and exhaust vents. Airflow studies, such as the release of smoke aerosols, should be used. The significance of airflow pattern studies depends on the purpose of sampling - for estimating worker intakes, warning of high concentrations. defacing airborne radioactive areas, testing for confinement of sealed radioactive materials. etc. When sampling air in rooms with complex airflow patterns, it may be useful to use qualitative airflow studies with smoke tubes, smoke candles or isostatic bubbles. The U.S. Nuclear Regulatory Commission - Regulatory Guide 8.25 [1]. suggests that an airflow study should be conducted after any changes at work area including changes in the setup of work areas, ventilation system changes, etc. The present work presents an airflow patterns study conducted in a typical room using two methods: a computer simulation and a qualitative test using a smoke tube

  17. Characterization of nuclear transmutations in materials irradiated test facilities

    International Nuclear Information System (INIS)

    This study presents a comparison of nuclear transmutation rates for candidate fusion first wall/blanket structural materials in available, fission test reactors with those produced in a typical fusion spectrum. The materials analyzed in this study include a vanadium alloy (V-4Cr-4Ti), a reduced activation martensitic steel (Fe-9Cr-2WVTa), a high conductivity copper alloy (Cu-Cr-Zr), and the SiC compound. The fission irradiation facilities considered include the EBR-II fast reactor, and two high flux mixed spectrum reactors, HFIR (High Flux Irradiation Reactor) and SM-3 (Russian reactor). The transmutation and dpa rates that occur in these test reactors are compared with the calculated transmutation and dpa rates characteristic of a D-T fusion first wall spectrum. In general, past work has shown that the displacement damage produced in these fission reactors can be correlated to displacement damage in a fusion spectrum; however, the generation of helium and hydrogen through threshold reactions [(n,x,α) and (n,xp)] are much higher in a fusion spectrum. As shown in this study, the compositional changes for several candidate structural materials exposed to a fast fission reactor spectrum are very low, similar to those for a characteristic fusion spectrum. However, the relatively high thermalized spectrum of a mixed spectrum reactor produces transmutation rates quite different from the ones predicted for a fusion reactor, resulting in substantial differences in the final composition of several candidate alloys after relatively short irradiation time

  18. Nuclear Power: The Market Test. Worldwatch Paper 57.

    Science.gov (United States)

    Flavin, Christopher

    Nuclear power was considered vital to humanity's future until just a short time ago. Since the late seventies, economic viability has joined a list of such issues as waste disposal and radiation hazards which call into question the future of nuclear power. This document discusses (in separate sections): (1) the selling of nuclear power, including…

  19. Sustainable land use planning at the Semipalatinsk Nuclear Test Site

    International Nuclear Information System (INIS)

    Full text: The UK Department for International Development (DFID) has recently agreed to support a project to develop a participatory sustainable land use plan for areas affected by nuclear weapons testing at Semipalatinsk. This three year project is expected to be initiated in April 2001 and will form one component of the United Nations Development Programme (UNDP) Semipalatinsk Rehabilitation Programme. The project will be undertaken by a combination of Kazakh organizations working with UK consultants and will meet its overall aim through the following main activities: Development of institutional capacity in data management and analysis; Provision of information and education on environmental contamination, hazards and risks; Development of a participatory land use planning process and piloting of the process in specific areas and communities around the test site; Integration of mineral resource extraction in the land planning process with a focus- on water resource and environmental protection and participatory approaches to resolving land use conflicts; Development of legislative tools to permit the implementation of environmental management of resource exploitation. The project will make use of both modern satellite-based imagery and more traditional methods to determine the potential for different land uses within the test site. The results obtained will be incorporated with additional information on land use. radiological and hydrological conditions at the test site through a geographical information system (GIS) provided by the project. The GIS will form the core component for collation and distribution of information on options available for use of different areas of the test site and its vicinity. A participatory rural appraisal, using tried and tested techniques, will identify local interest groups in land use planning and identify the details of their stake in the process. The groups will include owners-herders, employee-herders, and subsistence

  20. Mine seismicity and the Comprehensive Nuclear Test Ban Treaty

    Energy Technology Data Exchange (ETDEWEB)

    Chiappetta, F. [Blasting Analysis International, Allentown, PA (United States); Heuze, F.; Walter, W. [Lawrence Livermore National Lab., CA (United States); Hopler, R. [Powderman Consulting Inc., Oxford, MD (United States); Hsu, V. [Air Force Technical Applications Center, Patrick AFB, FL (United States); Martin, B. [Thunder Basin Coal Co., Wright, WY (United States); Pearson, C. [Los Alamos National Lab., NM (United States); Stump, B. [Southern Methodist Univ., Dallas, TX (United States); Zipf, K. [Univ. of New South Wales (Australia)

    1998-12-09

    Surface and underground mining operations generate seismic ground motions which are created by chemical explosions and ground failures. It may come as a surprise to some that the ground failures (coal bumps, first caves, pillar collapses, rockbursts, etc.) can send signals whose magnitudes are as strong or stronger than those from any mining blast. A verification system that includes seismic, infrasound, hydroacoustic and radionuclide sensors is being completed as part of the CTBT. The largest mine blasts and ground failures will be detected by this system and must be identified as distinct from signals generated by small nuclear explosions. Seismologists will analyze the seismic records and presumably should be able to separate them into earthquake-like and non earthquake-like categories, using a variety of so-called seismic discriminants. Non-earthquake essentially means explosion- or implosion-like. Such signals can be generated not only by mine blasts but also by a variety of ground failures. Because it is known that single-fired chemical explosions and nuclear explosion signals of the same yield give very similar seismic records, the non-earthquake signals will be of concern to the Treaty verification community. The magnitude of the mine-related events is in the range of seismicity created by smaller nuclear explosions or decoupled tests, which are of particular concern under the Treaty. It is conceivable that legitimate mining blasts or some mine-induced ground failures could occasionally be questioned. Information such as shot time, location and design parameters may be all that is necessary to resolve the event identity. In rare instances where the legitimate origin of the event could not be resolved by a consultation and clarification procedure, it might trigger on On-Site Inspection (OSI). Because there is uncertainty in the precise location of seismic event as determined by the International Monitoring System (IMS), the OSI can cover an area of up to 1

  1. Monitoring of natural revegetation of Semipalatinsk nuclear testing ground

    International Nuclear Information System (INIS)

    It is well known, that monitoring of natural revegetation of Semipalatinsk test site (STS) was carried out during period 1994-2002 at test areas (Experimental field, Balapan, Degelen). In this paper the peculiarities of vegetation cover of these test areas are observed. Thus, vegetation cover of Experimental field ground in the epicentre is completely destroyed. At present there are different stages of zonal steppe communities rehabilitation: in zones with γ-irradiation 11000-14000 μR/h the revegetation is not found; on the plots with γ-irradiation 8200-10000 μR/h rare species of Artemisia frigida are found; aggregation of plant (managed from 6000-7000 μR/h is observed; At the γ-irradiation 80-200 μR/h rarefied groups of bunch grass communities similar to the zonal steppe are formed and zonal bunch grass communities developed with 18-25 μR/h. Vegetation cover of Degelen hill tops and near-mouth ground in the results of underground nuclear expulsions are completely destroyed. Here there are three main kinds of vegetation: very stony gallery areas don't almost overgrow; at technogen tops near galleries the single plants, rare field groups and unclosed micro-phyto-biocenoses of weed and adventive species (Amaranthus retroflexus, Artemisia dracunculus, Laxctuca serriola, Chorispora sibirica etc.). On the Balapan are the revegetation is limited by high radiation pollution rate. Here cenose rehabilitation is presented by Artemisia marshalliana, Spita sareptana, Festuca valresiaca). In their paper florostic and phyrocoenitic diversity of STS's flora transformation is studied. Pattern distribution and migration of radionuclides in soils and vegetation cover is represented

  2. Resettlement of Bikini Atoll: US nuclear test site

    International Nuclear Information System (INIS)

    Bikini Atoll was one of two sites in the Marshall Islands that were used in the 1950's by the United States for testing nuclear weapons. The testing produced widespread radioactive contamination in Bikini and much of the Northern Marshall Islands. The Bikini people, relocated in 1946 before the test program began, have long desired to return to their homeland. Coral soil on Bikini Island makes cesium-137 (137Cs) much more available for plant uptake than do soils of North America and Europe. Hence, when locally grown crops mature and become available for consumption, the resulting body burden of 137Cs and the associated doses to humans exceeds federal guidelines. The dose from the terrestrial food ingestion pathway dominates all other pathways and contributes about 90% of the total dose to returning residents. We are, therefore, involved in cost-effective efforts to reduce the dose associated with resettlement. We have evaluated several measures, in addition to soil removal, to eliminate 137Cs from the soil and to reduce its uptake into food crops. The most effective, and the easiest to implement, is the application of potassium to the atoll soils. A dramatic reduction in 137Cs occurs in tropical fruits after applications of potassium-rich fertilizer to experimental soil plots. This treatment reduces the associated ingestion dose to about 5% of the pre-treatment levels, and this option avoids removal of the organic-rich surface soils. In addition, the added potassium increases plant productivity. We are now focusing on determining the duration of the effects of potassium treatment on 137Cs uptake into plants, and the rate of environmental loss of 137Cs in the atoll ecosystem. (author)

  3. Consolidation and disposal of nuclear test debris at the Nevada Test Site

    International Nuclear Information System (INIS)

    This paper discusses how numerous operational activities conducted at the Nevada Test Site (NTS) resulted in 24 fenced-off areas containing radioactively-contaminated debris. The debris consists of structural tower components, building debris, earthen materials, and equipment contaminated during atmospheric and underground testing of nuclear devices. Contaminated materials were consolidated, covered with clean fill, and fenced to reduce the area requiring controlled access and to provide additional radiation safety barriers. In 1980, disposal of the consolidated debris in subsidence craters, formed as a result of underground nuclear testing, was initiated. The waste materials are disposed using conventional landfill techniques where each layer of debris is covered with clean fill before additional waste materials are disposed. The waste is placed to within 3 m of the land surface and backfilled with compacted earthen material to the original grade. Requirements for air sampling, anticontamination, decontamination, and area access control are determined on a site-by-site basis due to the variety of conditions that exist

  4. Accuracy analysis of the CTBTO nuclear test detection scale and Improvement

    International Nuclear Information System (INIS)

    CTBTO (Comprehensive nuclear Test Ban Treaty Organization) is charge of nuclear test monitoring for nuclear non-proliferation. CTBTO has 170 seismic stations in operation in 76 countries in order to detect the artificial earthquake that was caused by an underground nuclear test. Korea use formula that is based on the equations that are used by the IMS (International Monitoring System) of CTBTO for analysis of explosive scale, and reflect the nature of the terrain, such as rock. But the expression for calculating the exact scale explosive is still un-established state. And generally CTBTO doesn't care about artificial explosive that is being received low-yield in accordance with the criteria of nuclear detection. But, at the time that North Korea conduct a nuclear test, it should not be overlooked that the scale of the earthquake detection criteria below. Because DPRK is trying to conceal their nuclear development capability, there are possibility of low-yield nuclear test or possibility of install a buffer to hide actual explosive scale. These radionuclide observations were consistent with a DPRK low-yield nuclear test on May 2010, even though no seismic signals from such a test have been detected. But there were a few times of low-yield (magnitude 1.39-1.93) occurred around DPRK nuclear test site at that time

  5. ESR dosimetry study of population in the vicinity of the Semipalatinsk Nuclear Test Site

    OpenAIRE

    Zhumadilov, Kassym; Ivannikov, Alexander; Stepanenko, Valeriy; Zharlyganova, Dinara; Toyoda, Shin; Zhumadilov, Zhaxybay; Hoshi, Masaharu

    2013-01-01

    A tooth enamel electron spin resonance (ESR) dosimetry study was carried out with the purpose of obtaining the individual absorbed radiation doses of population from settlements in the Semipalatinsk region of Kazakhstan, which was exposed to radioactive fallout traces from nuclear explosions in the Semipalatinsk Nuclear Test Site and Lop Nor test base, China. Most of the settlements are located near the central axis of radioactive fallout trace from the most contaminating surface nuclear test...

  6. Radionuclide Partitioning in an Underground Nuclear Test Cavity

    Energy Technology Data Exchange (ETDEWEB)

    Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

    2009-01-09

    In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors

  7. Development of Coolant Flow Simulation System for Nuclear Fuel Test Rigs

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jintae; Joung, Chang-Young; Heo, Sung-Ho; Kim, Ka-Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-01-15

    To remove heat generated during a burn-up test of nuclear fuels, the heat generation rate of nuclear fuels should be calculated accurately, and a coolant should be circulated in the test loop at an adequate flow rate. HANARO is an open pool-type reactor with an independent test loop for the burn-up test of nuclear fuels. A test rig is installed in the test loop, and a coolant is circulated through the test loop to maintain the temperature of the nuclear fuel rods within a desired temperature during an irradiation test. The components and sensors in the test rig can be broken or malfunction owing to the flow-induced vibration. In this study, a coolant flow simulation system was developed to verify and confirm the soundness of components and sensors assembled in the test rig with a high flow rate of the coolant.

  8. Applications of optical fibers in nuclear test diagnostics

    International Nuclear Information System (INIS)

    Two new plasma diagnostic experiments have been successfully fielded on nuclear device tests at NTS. Both systems rely on the unique advantages provided by optical fiber technology and both systems provide new diagnostic capabilities that previously were beyond the state-of-the-art in coaxial cable systems. One system addresses the need to record e wide bandwidth data on gamma-ray sources. Over the long (< 1 km) distances that characterize NTS testing, the bandwidth of coaxial cable systems is usually limited to < 200 to 400 MHz even with extensive equalization. The new system uses the Cerenkov process to generate light in a converter material. High bandwidth fibers and detectors are used to approach a 1-GHz bandwidth. In this case fibers provided the bandwidth capability. The second system provides time and space resolution of a neutron source on a fast (ns) time scale. Previous systems have utilized either an array of neutron detectors with individual coaxial cables or a fast scintillator viewed by a gated image intensifier. For a large number of channels, the coaxial system becomes very costly and is subject to potentially severe EMI concerns. The gated intensifier system requires complex electronics and accurate timing and can be affected by EMI. An alternative system is described which provides continuous time coverage with limited spatial resolution. Complete freedom from EMI is achieved through the use of optical data collection and transmission. The optical fibers offered a major (2 to 3 times) cost savings and a large weight savings relative to the coax system. Each system is discussed

  9. A Hydrogen Containment Process For Nuclear Thermal Engine Ground Testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    A hydrogen containment process was proposed for ground testing of a nuclear thermal engine. The hydrogen exhaust from the engine is contained in two unit operations: an oxygen-rich burner and a tubular heat exchanger. The burner burns off the majority of the hydrogen, and the remaining hydrogen is removed in the tubular heat exchanger through the species recombination mechanism. A multi-dimensional, pressure-based multiphase computational fluid dynamics methodology was used to conceptually sizing the oxygen-rich burner, while a one-dimensional thermal analysis methodology was used to conceptually sizing the heat exchanger. Subsequently, a steady-state operation of the entire hydrogen containment process, from pressure vessel, through nozzle, diffuser, burner and heat exchanger, was simulated numerically, with the afore-mentioned computational fluid dynamics methodology. The computational results show that 99% of hydrogen reduction is achieved at the end of the burner, and the rest of the hydrogen is removed to a trivial level in the heat exchanger. The computed flammability at the exit of the heat exchanger is less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process.

  10. Ionospheric disturbances locate the 2009 North Korean underground nuclear test

    Science.gov (United States)

    Park, J.; von Frese, R. R.; G-Brzezinska, D. A.; Morton, Y.; Gaya-Pique, L. R.

    2011-12-01

    Ionospheric disturbances from the North Korean underground nuclear explosion (UNE) of 25 May 2009 were detected using the total electron content (TEC) measurements from the Global Navigation Satellite System (GNSS). The TEC measurements were derived from the ionospheric delay of the GNSS signals and identified traveling ionospheric disturbances (TID) that can be attributed to the UNE. Taking three point numerical derivatives of the TEC measurements isolated the TIDs with propagation speeds of roughly 150 - 400 m/s at stations located about 365 km to 1330 km from the UNE. TIDs were detected at eleven stations where the statistical probability for these TIDs to have occurred randomly across the GNSS array was found to be less than one chance in 1033 chances. Nearly 1300 TID samples from these GNSS stations were tested to confirm the strong statistical uniqueness of the array signature. Furthermore, the GNSS observations mapped ionospheric winds for adjusting the TID velocities to locate the UNE to within about 2.7 km of its seismically determined epicenter.

  11. Preliminary results of sequential monitoring of simulated clandestine graves in Colombia, South America, using ground penetrating radar and botany.

    Science.gov (United States)

    Molina, Carlos Martin; Pringle, Jamie K; Saumett, Miguel; Hernández, Orlando

    2015-03-01

    In most Latin American countries there are significant numbers of missing people and forced disappearances, 68,000 alone currently in Colombia. Successful detection of shallow buried human remains by forensic search teams is difficult in varying terrain and climates. This research has created three simulated clandestine burial styles at two different depths commonly encountered in Latin America to gain knowledge of optimum forensic geophysics detection techniques. Repeated monitoring of the graves post-burial was undertaken by ground penetrating radar. Radar survey 2D profile results show reasonable detection of ½ clothed pig cadavers up to 19 weeks of burial, with decreasing confidence after this time. Simulated burials using skeletonized human remains were not able to be imaged after 19 weeks of burial, with beheaded and burnt human remains not being able to be detected throughout the survey period. Horizontal radar time slices showed good early results up to 19 weeks of burial as more area was covered and bi-directional surveys were collected, but these decreased in amplitude over time. Deeper burials were all harder to image than shallower ones. Analysis of excavated soil found soil moisture content almost double compared to those reported from temperate climate studies. Vegetation variations over the simulated graves were also noted which would provide promising indicators for grave detection. PMID:25596556

  12. Dietary supplements: International legal framework and adulteration profiles, and characteristics of products on the Brazilian clandestine market.

    Science.gov (United States)

    da Justa Neves, Diana Brito; Caldas, Eloisa Dutra

    2015-10-01

    The objectives of this work were to evaluate current legislation on dietary supplements in the United States, the European Union and Brazil, and the profile of adulterated and/or irregular products on these markets. Due to a less restrictive legal framework, a supplement product that is freely available in the US may be considered a drug or even be proscribed in the EU and Brazil, thus giving rise to a clandestine market based on smuggling. From 2007 to 2014, the United States Food and Drug Administration reported 572 cases of supplement adulterations in the country, mainly products for sexual enhancement (41.6%). Data from the European Union Rapid Alert System for Food and Feed showed 929 adulterations during the same period, over 40% due to unauthorized ingredients or undeclared medicines. From 2007 to 2013, the Brazilian Federal Police Department seized 5470 supplement products, 92.2% with an American-declared origin. Qualitative chemical analyses performed on 2898 products found 180 adulterations, 41.1% due to undeclared drugs, mainly anabolic steroids, anorectics and products for erectile dysfunction, all considered medicines in Brazil. Educating the public regarding the potential risks they are taking when consuming adulterated or irregular products is necessary to protect the health of consumers. PMID:26107294

  13. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

  14. Monju core physics test analysis with various nuclear data libraries

    International Nuclear Information System (INIS)

    JAEA has been re-analyzing Monju core physics tests to validate the JAEA's neutronics calculation system to be used in the next Monju core physics tests. Precedent results presented in PHYSOR2008 have demonstrated the validity of the system based on the basic physical parameters, such as criticality, control rod worth, isothermal temperature coefficient, and power coefficient. This paper is a continuation of the validation study focusing on the other parameters, such as fixed absorber reactivity worth, fuel sub-assembly reactivity worth, coolant reactivity worth, burnup coefficient, and reaction rate. The fixed absorber reactivity worth is a reactivity induced by the replacement of a blanket sub-assembly to a fixed absorber sub-assembly. The fuel sub-assembly reactivity worth is a reactivity induced by the replacement of a fuel sub-assembly to a non-fissile dummy sub-assembly. The coolant reactivity worth is a reactivity induced by the replacement of a non- fissile dummy sub-assembly containing sodium to that containing helium. The reaction rate data include the reaction rate ratio of 238U capture to 239Pu fission. Each of the data is useful to check the calculation system in a particular aspect. For example, the first two data are suitable to check the calculation accuracy of a blanket region and a fuel sub-assembly, respectively. The parameters are simulated using the JAEA's neutronics calculation system with various nuclear date libraries, JENDL-3.2, JENDL-3.3, JENDL/AC-2008, JEFF-3.1, and ENDF/B-VII. A continuous energy Monte Carlo calculation code, MVP, is employed to check calculation methods. Figure 1 shows an example of the C/E (Calculation over Experiment) values. The C/E values are within experimental errors for the fixed absorber reactivity worth and the fuel sub- assembly reactivity worth. Those for the burnup reactivity coefficient are around the experimental error and show a tendency of overestimation. About the comparison with the Monte Carlo

  15. Analysis of North Korea's Nuclear Tests under Prospect Theory

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Myung; Ryu, Jae Soo; Lee, Kwang Seok; Lee, Dong Hoon; Jun, Eunju; Kim, Mi Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    North Korea has chosen nuclear weapons as the means to protect its sovereignty. Despite international society's endeavors and sanctions to encourage North Korea to abandon its nuclear ambition, North Korea has repeatedly conducted nuclear testing. In this paper, the reason for North Korea's addiction to a nuclear arsenal is addressed within the framework of cognitive psychology. The prospect theory addresses an epistemological approach usually overlooked in rational choice theories. It provides useful implications why North Korea, being under a crisis situation has thrown out a stable choice but taken on a risky one such as nuclear testing. Under the viewpoint of prospect theory, nuclear tests by North Korea can be understood as follows: The first nuclear test in 2006 is seen as a trial to escape from loss areas such as financial sanctions and regime threats; the second test in 2009 was interpreted as a consequence of the strategy to recover losses by making a direct confrontation against the United States; and the third test in 2013 was understood as an attempt to strengthen internal solidarity after Kim Jong-eun inherited the dynasty, as well as to enhance bargaining power against the United States. Thus, it can be summarized that Pyongyang repeated its nuclear tests to escape from a negative domain and to settle into a positive one. In addition, in the future, North Korea may not be willing to readily give up its nuclear capabilities to ensure the survival of its own regime.

  16. Completion of Flow Interruption Capability Test Stand for Functional Qualification Test of Valves Used in Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    CHENG; Dao-xi; QI; Xiao-guang; ZHAI; Wei-ming; YANG; Bing; ZHOU; Ping

    2013-01-01

    The flow interruption capability test of valve is used for researching the capability of the valves used in nuclear power plants emergently shut off the flow,when the reactor loop is in emergency situations,especially in the design basis accident conditions.This test is one of the most difficult tests in the functional

  17. Non-destructive Testing Dummy Nuclear Fuel Rods by Neutron Radiography

    Institute of Scientific and Technical Information of China (English)

    WEI; Guo-hai; HAN; Song-bai; HE; Lin-feng; WANG; Yu; WANG; Hong-li; LIU; Yun-tao; CHEN; Dong-feng

    2013-01-01

    As a unique non-destructive testing technique,neutron radiography can be used to measure nuclear fuel rods with radioactivity.The images of the dummy nuclear fuel rods were obtained at the CARR.Through imaging analysis methods,the structure defections,the hydrogen accumulation in the cladding and the 235U enrichment of the pellet were studied and analyzed.Experiences for non-destructive testing real PWR nuclear fuel rods by NR

  18. Images processing in hostile nuclear environments. Experimental CCD cameras tests results for robotic operations

    International Nuclear Information System (INIS)

    This paper describes succinctly the hostile aspect of nuclear environment for visual sensors and transmissions. It approaches the new field of nuclear Robotic and its constraints about vision process. Tolerance tests of CCD cameras in gamma radiations environment are displayed: - gamma dosimetry measures, - electrical measurement process, - views during testing, - degradations and better tolerance hypothesis

  19. Non-destructive-Testing of Nuclear Fuel Element by Means of Neutron Imaging Technique

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Nuclear fuel element is the key component of nuclear reactor. People have to make strictly testing of the element to make sure the reactor operating safely. Neutron imaging is one of Non-destructive-Testing (NDT) techniques, which are very important techniques for

  20. Under a cloud of secrecy: the French nuclear tests in the Southeastern Pacific

    International Nuclear Information System (INIS)

    The use of the Pacific as a testing ground for nuclear weapons is 1 of the darkest chapters in the history of the region. Before the Partial Test Ban Treaty went into effect in 1963, the USA had tested at least 103 nuclear bombs in the region. After 1963, the Americans, British and Soviets moved their nuclear testing programs out of the Pacific permanently. Today, only the French insist on testing their nuclear bombs in the Pacific, on 2 Polynesian islands, Moruroa and Fangataufa. Since 1966, the French have exploded at least 105 bombs. The devastation caused by this testing is a continuing source of controversy in the South Pacific. Relevant fallout data from all the tests have never been made public by the French government and the actual extent of the contamination of French Polynesia and its neighbors from radioactive fallout remains unknown

  1. Hydrogen Wave Heater for Nuclear Thermal Propulsion Component Testing Project

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA has identified Nuclear Thermal Propulsion (NTP) as a propulsion concept which could provide the fastest trip times to Mars and as the preferred concept for...

  2. Nuclear Matrix Elements for Tests of Fundamental Symmetries

    CERN Document Server

    Brown, B A; Robledo, L M; Romalis, M V; Zelevinsky, V

    2016-01-01

    The nuclear matrix elements for the momentum quadrupole operator and nucleon spin operator are important for interpretation of precision atomic physics experiments that search for violations of Lorentz and CPT symmetry and for new spin-dependent forces. We use the configuration-interaction nuclear shell model and self-consistent mean field theory to calculate the relevant matrix elements in $^{21}$Ne, $^{131}$Xe, and $^{201}$Hg. We find that the spin expectation values in these nuclei are dominated by the odd neutron, while the quadrupole moment of the nucleon momentum, M, has comparable neutron and proton contributions. These are the first microscopic calculations of the nuclear matrix elements for the momentum quadrupole tensor that go beyond the single-particle estimate. We show that they are strongly suppressed by the many-body correlations, in contrast to the well known enhancement of the spatial quadrupole nuclear matrix elements.

  3. Barometric pressure transient testing applications at the Nevada Test Site. Nuclear chimney analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, J.M.

    1985-12-01

    Investigations of barometric pressure testing of NTS nuclear chimneys were reviewed. This review includes the models used in the interpretation, methods of analysis, and results. Analytic and semi-analytic models were presented and applied to both historical data and new data taken for this current project. An interpretation technique based on non-linear least squares methods was used to analyze this data in terms of historic and more recent chimney models. Finally, a detailed discussion of radioactive gas transport due to surface barometric pressure fluctuations was presented. This mechanism of transport, referred to as ''barometric pumping,'' is presented in terms of conditions likely to be encountered at the NTS. The report concludes with a discussion of the current understanding of gas flow properties in the alluvial and volcanic areas of the NTS, and suggestions for future efforts directed toward increasing this understanding are presented.

  4. Barometric pressure transient testing applications at the Nevada Test Site. Nuclear chimney analysis. Final report

    International Nuclear Information System (INIS)

    Investigations of barometric pressure testing of NTS nuclear chimneys were reviewed. This review includes the models used in the interpretation, methods of analysis, and results. Analytic and semi-analytic models were presented and applied to both historical data and new data taken for this current project. An interpretation technique based on non-linear least squares methods was used to analyze this data in terms of historic and more recent chimney models. Finally, a detailed discussion of radioactive gas transport due to surface barometric pressure fluctuations was presented. This mechanism of transport, referred to as ''barometric pumping,'' is presented in terms of conditions likely to be encountered at the NTS. The report concludes with a discussion of the current understanding of gas flow properties in the alluvial and volcanic areas of the NTS, and suggestions for future efforts directed toward increasing this understanding are presented

  5. Space Nuclear Thermal Propulsion Test Facilities Subpanel. Final report

    International Nuclear Information System (INIS)

    On 20 Jul. 1989, in commemoration of the 20th anniversary of the Apollo 11 lunar landing, President George Bush proclaimed his vision for manned space exploration. He stated, 'First for the coming decade, for the 1990's, Space Station Freedom, the next critical step in our space endeavors. And next, for the new century, back to the Moon. Back to the future. And this time, back to stay. And then, a journey into tomorrow, a journey to another planet, a manned mission to Mars.' On 2 Nov. 1989, the President approved a national space policy reaffirming the long range goal of the civil space program: to 'expand human presence and activity beyond Earth orbit into the solar system.' And on 11 May 1990, he specified the goal of landing Astronauts on Mars by 2019, the 50th anniversary of man's first steps on the Moon. To safely and ever permanently venture beyond near Earth environment as charged by the President, mankind must bring to bear extensive new technologies. These include heavy lift launch capability from Earth to low-Earth orbit, automated space rendezvous and docking of large masses, zero gravity countermeasures, and closed loop life support systems. One technology enhancing, and perhaps enabling, the piloted Mars missions is nuclear propulsion, with great benefits over chemical propulsion. Asserting the potential benefits of nuclear propulsion, NASA has sponsored workshops in Nuclear Electric Propulsion and Nuclear Thermal Propulsion and has initiated a tri-agency planning process to ensure that appropriate resources are engaged to meet this exciting technical challenge. At the core of this planning process, NASA, DOE, and DOD established six Nuclear Propulsion Technical Panels in 1991 to provide groundwork for a possible tri-agency Nuclear Propulsion Program and to address the President's vision by advocating an aggressive program in nuclear propulsion. To this end the Nuclear Electric Propulsion Technology Panel has focused it energies

  6. Prohibiting and Preventing Nuclear Explosions: Background Information for Parliamentarians on the Comprehensive Nuclear-Test-Ban Treaty (CTBT)

    International Nuclear Information System (INIS)

    The object and purpose of the CTBT is to ban comprehensively nuclear weapon test explosions and any other nuclear explosion in any environment in an effectively verifiable manner. The CTBT aims at eliminating nuclear weapons by constraining the development and qualitative improvement of new or more advanced nuclear weapons. It plays a crucial role in the prevention of nuclear proliferation and in nuclear disarmament, thus contributing to a safer and more secure world. When the Treaty enters into force it will establish a treaty-implementing body (the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO)), including an on-site inspection mechanism and confidence-building measures as well as an International Monitoring System (IMS) and International Data Centre (IDC). The IMS and IDC are already being created and are being provisionally operated during the preparatory phase by the Preparatory Commission for the CTBTO and its Provisional Technical Secretariat in Vienna. Seismic, hydroacoustic, infrasound and radionuclide data are collected through the stations of the IMS and transmitted to Member States via the IDC. The IDC also processes the raw data received from the stations to derive objective products and services which will support the Treaty verification responsibilities. If the collected and analysed data indicate an ambiguous event, States may address concerns about possible noncompliance with the Treaty through a consultation and clarification process after it enters into force and may request an on-site inspection by the CTBTO.

  7. The new technologies and infrastructure conversion of nuclear testing in Kazakhstan

    International Nuclear Information System (INIS)

    It is known, that in August, 1991, in accordance with Decree by the Kazakhstan President, the Semipalatinsk test site (STS) was shut down, and practical works on its conversion were initiated. In 1991 the decision on creation of the Kazakhstan National Nuclear Center (KNNC) on a base of the test site scientific and industrial enterprises and Inst. of Nuclear Physics was taken. In 1993 within frame KNNC three new institutes (Inst. of Atomic Energy, Inst. of Geophysical Research, Inst. of Radiation Safety and Ecology) were created. Owing to this, at the condition of USSR disintegration and liquidation of military division in test site territory, high-qualified personnel was saved, the facilities that represent nuclear danger were left under operation and surveillance, and the full-scale program of STS conversion was developed and put into life. At present guidelines for the major research activities at KNNC on conversion program are as follows: liquidation of consequences of nuclear tests; liquidation of technological structure used before for preparation and implementation of nuclear weapons tests; creation of technology, equipment and locations for receipt and storage of radioactive wastes; working out the concept of nuclear power development in Kazakhstan; investigation of the behaviour of melted reactor core in view of potential heavy accidents at nuclear power plants; development of technique and means for detection of nuclear test in the world, continuous control for nuclear explosions; experimental works on investigation of behaviour of the materials-candidates for role of constructional materials for the thermonuclear reactor ITER; creation of high-technology industries. These and other activities undertaken in this respect allow to attract considerable foreign investments, to create in Kurchatov city hundreds of additional working places.The Government support rendered to KNNC in future will allow to expand substantially this area of activities as well as to

  8. Concept for testing fusion first wall/blanket systems in existing nuclear facilities

    International Nuclear Information System (INIS)

    A novel concept to produce a reasonable simulation of a fusion first wall/blanket test environment (except the 14 MeV neutron component) employing an existing nuclear facility is presented. Preliminary results show that an asymmetric, nuclear test environment with surface and volumetric heating rates similar to those expected in a fusion first wall/blanket or divertor chamber surface appears feasible. The proposed concept takes advantage of nuclear reactions within the annulus of a test space (15 cm in diameter and approximately 100 cm high) to provide an energy flux to the surface of a test module

  9. Hanford spent nuclear fuel hot conditioning system test procedure

    International Nuclear Information System (INIS)

    This document provides the test procedures for cold testing of the prototype Hot Conditioning System (HCS) at the 306E Facility. The primary objective of this testing is to confirm design choices and provide data for the detailed design package prior to procurement of the process equipment. The current scope of testing in this document includes a fabricability study of the HCS, equipment performance testing of the HCS components, heat-up and cool-down cycle simulation, and robotic arm testing

  10. Possibilities of Kazakhstan experimental base for space nuclear reactors elements testing

    International Nuclear Information System (INIS)

    To the mid of 70-th in Kazakhstan the surface developing base for space nuclear reactors elements testing was created. The base consists of three test complexes. Two of them - the complexes of test reactors 'Baikal-1' and IGR - are situating on the Semipalatinsk test site, and the third one - complex of WWR-K research reactor - is situating in Alatau village nearby to Almaty city. On 'Baikal-1' and IGR complexes the testings for fuel elements, fuel assemblies, modules and prototypes of nuclear rocket engine reactor and nuclear energetic engine units with turbine-engine energy transmission on the base solid-phase reactor were carrying out. On the WWR-K reactor complex the testing of power generating channels of thermal-emission transmission reactors were conducted. In the paper the assessment of up-to-date experimental base status and it possibilities for further using in space nuclear energy field are given

  11. 78 FR 71676 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Final Report”

    Science.gov (United States)

    2013-11-29

    ... COMMISSION NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at Nuclear Power Plants, Final Report..., ``Guidelines for Inservice Testing at Nuclear Power Plants,'' and subtitled ``Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power...

  12. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    International Nuclear Information System (INIS)

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author)

  13. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  14. 3D - Acquisition systems - test in Chooz B nuclear plant

    International Nuclear Information System (INIS)

    EDF needs 3D-acquisition systems to get the precise geometry of critical nuclear spaces in order to prepare computer simulations of operations in these areas. The simulations must lead to an increase of the efficiency of the operation. The acquisition of the 3-D geometry can be done using 3D-acquisition systems. To answer the needs of the Construction Division, four different systems are compared by the Research Division in Chooz B nuclear plant in order to determine the right solution for each 3D-acquisition problem

  15. High Fidelity, Fuel-Like Thermal Simulators for Non-Nuclear Testing: Analysis and Initial Test Results

    Science.gov (United States)

    Bragg-Sitton, Shannon M.; Dickens, Ricky; Dixon, David; Kapernick, Richard

    2007-01-01

    Non-nuclear testing can be a valuable tool in the development of a space nuclear power system, providing system characterization data and allowing one to work through various fabrication, assembly and integration issues without the cost and time associated with a full ground nuclear test. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Testing with non-optimized heater elements allows one to assess thermal, heat transfer. and stress related attributes of a given system, but fails to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. High fidelity thermal simulators that match both the static and the dynamic fuel pin performance that would be observed in an operating, fueled nuclear reactor can vastly increase the value of non-nuclear test results. With optimized simulators, the integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and fueled nuclear testing. By implementing a neutronic response model to simulate the dynamic response that would be expected in a fueled reactor system, one can better understand system integration issues, characterize integrated system response times and response characteristics and assess potential design improvements at relatively small fiscal investment. Initial conceptual thermal simulator designs are determined by simple one-dimensional analysis at a single axial location and at steady state conditions; feasible concepts are then input into a detailed three-dimensional model for comparison to expected fuel pin performance. Static and dynamic fuel pin performance for a proposed reactor design is determined using SINDA/FLUINT thermal analysis software, and comparison is made between the expected nuclear performance and the performance of conceptual thermal simulator designs. Through a series of iterative analyses, a conceptual high fidelity design is developed

  16. Development of Induction Brazing System for Sealing Instrumentation Feed through Part of Nuclear Fuel Test Rig

    International Nuclear Information System (INIS)

    To test the performance of nuclear fuels, coolant needs to be circulated through the test rig installed in the test loop. Because the pressure and temperature of the coolant is 15.5 MPa and 300 .deg. C respectively, coolant sealing is one of the most important processes in fabricating a nuclear fuel test rig. In particular, 15 instrumentation cables installed in a test rig pass through the pressure boundary, and brazing is generally applied as a sealing method. In this study, an induction brazing system has been developed using a high frequency induction heater including a vacuum chamber. For application in the nuclear field, BNi2 should be used as a paste, and optimal process variables for Ni brazing have been found by several case studies. The performance and soundness of the brazed components has been verified by a tensile test, cross section test, and sealing performance test

  17. General discrimination technique to determine between earthquake and nuclear test with seismic data

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) was developed to ban of any nuclear weapon test explosion moreover will restrict the development and qualitative improvement of nuclear weapons and end the development of advanced new types of these weapons. The Treaty provides for a comprehensive global verification regime, which includes an International Monitoring System (IMS). The IMS comprises a network of 321 monitoring stations and 16 radionuclide laboratories that monitor the Earth for evidence of nuclear explosions, which cover underground, underwater and atmosphere environments. Presently, Malaysia receives seismic, infrasound, hydroacoustic and radionuclide data from the International Data Centre (IDC) of the CTBT. In order to maximise the use of the data for the purposes of the CTBT, the Malaysian Nuclear Agency is developing capability to analyse the data in order to detect nuclear weapon test, with an initial focus on the seismic data. Through the CTBT IMS, seismic data is constantly being obtained to monitor and detect nuclear explosions. However, in the process, other natural and man-made activities that generate seismic waves, especially earthquakes and large man-made explosions, are also detectable through the IMS, and need to be differentiated and discriminated before any nuclear explosions can be identified. The detection capability by using seismological methods was proven through simulated explosion tests at selected nuclear weapon test sites. This is supported by data previously collected from a total of 2089 nuclear weapon tests that have been carried out globally, out of which 1567 were underground, 514 in the atmosphere, including outer space, and 8 underwater. The discrimination of seismic data to detect nuclear explosions from natural earthquake and explosions can be undertaken through the identification of the epicentre location, hypocentre depth, magnitude and short-period discrimination of the seismic events. (Author)

  18. Subcritical tests - nuclear weapon testing under the Comprehensive Test Ban Treaty; Subkritiske tester - kjernevaapentesting under avtalen om fullstendig proevestans

    Energy Technology Data Exchange (ETDEWEB)

    Hoeibraaten, S

    1998-10-01

    The report discusses possible nuclear weapons related experiments and whether these are permitted under the 1996 Comprehensive Test Ban Treaty (CTBT). The term ''subcritical experiments'' as used in the United States includes experiments in which one studies fissile materials (so far only plutonium) under extreme conditions generated by conventional high explosives, and in which a self-sustained chain reaction never develops in the fissile material. The known facts about the American subcritical experiments are presented. There is very little reason to doubt that these experiments were indeed subcritical and therefore permitted under the CTBT. Little is known about the Russian efforts that are being made on subcritical experiments.

  19. High Fidelity Thermal Simulators for Non-Nuclear Testing: Analysis and Initial Results

    Science.gov (United States)

    Bragg-Sitton, Shannon M.; Dickens, Ricky; Dixon, David

    2007-01-01

    Non-nuclear testing can be a valuable tool in the development of a space nuclear power system, providing system characterization data and allowing one to work through various fabrication, assembly and integration issues without the cost and time associated with a full ground nuclear test. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Testing with non-optimized heater elements allows one to assess thermal, heat transfer, and stress related attributes of a given system, but fails to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. High fidelity thermal simulators that match both the static and the dynamic fuel pin performance that would be observed in an operating, fueled nuclear reactor can vastly increase the value of non-nuclear test results. With optimized simulators, the integration of thermal hydraulic hardware tests with simulated neutronie response provides a bridge between electrically heated testing and fueled nuclear testing, providing a better assessment of system integration issues, characterization of integrated system response times and response characteristics, and assessment of potential design improvements' at a relatively small fiscal investment. Initial conceptual thermal simulator designs are determined by simple one-dimensional analysis at a single axial location and at steady state conditions; feasible concepts are then input into a detailed three-dimensional model for comparison to expected fuel pin performance. Static and dynamic fuel pin performance for a proposed reactor design is determined using SINDA/FLUINT thermal analysis software, and comparison is made between the expected nuclear performance and the performance of conceptual thermal simulator designs. Through a series of iterative analyses, a conceptual high fidelity design can developed. Test results presented in this paper correspond to a "first cut" simulator design for a potential

  20. Sample and injection manifolds used to in-place test of nuclear air-cleaning system

    International Nuclear Information System (INIS)

    Objective: According to the regulations of nuclear safety rules and related standards, in-place test of the nuclear air-cleaning systems should be carried out before and during operation of the nuclear facilities, which ensure them to be in good condition. In some special conditions, the use of sample and injection manifolds is required to make the test tracer and ventilating duct air fully mixed, so as to get the on-spot typical sample. Methods: This paper introduces the technology and application of the sample and injection manifolds in nuclear air-cleaning system. Results: Multi point injection and multi point sampling technology as an effective experimental method, has been used in a of domestic and international nuclear facilities. Conclusion: The technology solved the problem of uniformly of on-spot injection and sampling,which plays an important role in objectively evaluating the function of nuclear air-cleaning system. (authors)

  1. Low-level nuclear waste tested for fertilizer value

    International Nuclear Information System (INIS)

    The nuclear power industry keeps coming up with proposals for getting rid of radioactive waste - burying it deep in the ground, sinking it at sea and even sending it into space reports Common Cause magazine under a headline, The Latest in Recycling. At its Sequoyah Fuels facility in Oklahoma, Kerr-McGee manufactures fuel for nuclear power plants, generating a low-level radioactive liquid waste product called raphinate. After processing to remove radioactive substances, Kerr-McGee has gotten approval from the Nuclear Regulatory Commission to use the nitrogen-rich residue as a fertilizer - but not to market it. As a result, Kerr-McGee is reported to be buying up thousands of acres of land on which to spread raphinate. The acreage is used to grow hay, which the company has gotten an okay to sell. The recycling effort hasn't exactly won neighborhood friends for the company, noted Common Cause. According to Kerr-McGee's corporate communications direct, When you say to somebody, Sequoyah Fuels is putting nuclear waste (on farmland), people jump up a wall

  2. Visualization test facility of nuclear fuel rod emergency cooling system

    International Nuclear Information System (INIS)

    The nuclear reactors safety is determined according to their protection against the consequences that may result from postulated accidents. The Loss of Coolant Accident (LOCA) is one the most important design basis accidents (DBA). The failure may be due to rupture of the primary loop piping. Another accident postulated is due to lack of power in the pump motors in the primary circuit. In both cases the reactor shut down automatically due to the decrease of reactivity to maintain the fissions, and to the drop of control rods. In the event of an accident it is necessary to maintain the coolant flow to remove the fuel elements residual heat, which remains after shut down. This heat is a significant amount of the maximum thermal power generated in normal operation (about 7%). Recently this event has been quite prominent in the press due to the reactor accident in Fukushima nuclear power station. This paper presents the experimental facility under rebuilding at the Thermal Hydraulic Laboratory of the Nuclear Technology Development Center (CDTN) that has the objective of monitoring and visualization of the process of emergency cooling of a nuclear fuel rod simulator, heated by Joule effect. The system will help the comprehension of the heat transfer process during reflooding after a loss of coolant accident in the fuel of light water reactor core. (author)

  3. Ground Test Facility for Propulsion and Power Modes of Nuclear Engine Operation

    Energy Technology Data Exchange (ETDEWEB)

    Michael, WILLIAMS

    2004-11-22

    Existing DOE Ground Test Facilities have not been used to support nuclear propulsion testing since the Rover/NERVA programs of the 1960's. Unlike the Rover/NERVA programs, DOE Ground Test facilities for space exploration enabling nuclear technologies can no longer be vented to the open atmosphere. The optimal selection of DOE facilities and accompanying modifications for confinement and treatment of exhaust gases will permit the safe testing of NASA Nuclear Propulsion and Power devices involving variable size and source nuclear engines for NASA Jupiter Icy Moon Orbiter (JIMO) and Commercial Space Exploration Missions with minimal cost, schedule and environmental impact. NASA site selection criteria and testing requirements are presented.

  4. No conceivable injury. [Nuclear weapons tests in Australia, 1952-1957

    Energy Technology Data Exchange (ETDEWEB)

    Milliken, R.

    1986-01-01

    Between 1952 and 1957 Britain conducted 12 nuclear tests in Australia in order to develop a nuclear weapon capability. At that time a special relationship existed between the two countries with Australians keen to help. However, an Australian Royal Commission investigating British nuclear tests in the mid-eighties gave attention to some aspects of the tests which had been kept secret, especially by Britain. In particular the contamination of the sites, especially at Maralinga, a sacred place of the Aborigines, is highlighted. The Royal Commission indeed recommended that Britain should decontaminate the site and Australia should compensate the Aborigines. Doing this, however, would acknowledge the responsibility of the tests for health problems of British and Australian servicemen due to radiation exposure. This was postponed while another report was commissioned from another body. The history of the nuclear tests and their consequences in both human and political terms is chronicled.

  5. Development of High Fidelity, Fuel-Like Thermal Simulators for Non-Nuclear Testing

    Science.gov (United States)

    Bragg-Sitton, Shannon; Dickens, Ricky; Dixon, David

    2007-01-01

    This viewgraph presentation reviews the development of a simulator for non-nuclear tests for the development of a space nuclear power system. The development of the Instrumented Thermal Simulator is to assist in developing an understanding of individual components and integrated system operation without the cost, time, safety concerns associated with nuclear testing. The presentation shows the design, the electrical integration, the hardware, and the assembly of the simulators. There are slides that show the test plan, the analysis, and the initial results.

  6. Space nuclear power system concepts and the test facility needs/programmatic requirements

    International Nuclear Information System (INIS)

    This paper gives an overview of the planning needs for the SP-100 and Megawatt Class Nuclear Space Power Systems programs. Factors of concern include: establishment of mission performance test goals; determination of current Federal Order requirements; compliance with applicable institutional and regulatory requirements, especially those related to site environmental qualification; analysis of lessons learned from the commercial nuclear power, NERVA and SNAP programs; determination of needed technical program support services; analysis of regulatory requirements for similar nuclear programs; establishment of test program safeguards and security; analysis of public health and safety; determination of site program readiness; and determination of public acceptance of the space program and the proposed test site

  7. Test validation of nuclear and fossil fuel control operators

    International Nuclear Information System (INIS)

    To establish job relatedness, one must go through a procedure of concurrent and predictive validation. For concurrent validity a group of employees is tested and the test scores are related to performance concurrently or during the same time period. For predictive validity, individuals are tested but the results of these tests are not used at the time of employment. The tests are sealed and scored at a later date, and then related to job performance. Job performance data include ratings by supervisors, actual job performance indices, turnover, absenteeism, progress in training, etc. The testing guidelines also stipulate that content and construct validity can be used

  8. Static and dynamic performance tests of nuclear powered ship Mutsu reactor (report on nuclear ship Mutsu power-up tests)

    International Nuclear Information System (INIS)

    The power-up tests of the Mutsu reactor were performed from March 29th 1990 to December 14th. The tests were divided into six phases: The tests Phase 0 and Phase 1 were done in the state that the ship was moored at the quay of Sekinehama port in March and April; The tests Phase 2, Phase 3, Phase 4, and Phase 5 were done on the Pacific Ocean from July to December. Present report describes the test results on the static and dynamic plant performance. On static plant performance tests, there are 13 test items including measurements of primary system heat balance at low and high power levels, a virgin run of feed water pump with SG steam, a change-over test of steam supply of auxiliary boiler to SG. On the dynamic plant performance, there are 11 test items including a test of reactor power auto-control system, a test of main feed water auto-control system, a test of small load variation, a load increasing test, a turbine trip test, tests of ahead and astern maneuvering, a test of single loop operation, and a reactor scram test. The reactor power for each item's test was increased step by step from zero power to the goal of rated power of 100 %, 36 MWt. In order to confirm proper reactor system performance, criteria were laid down for the static and dynamic tests: for example, (1) reactor scram shall not occur, (2) pressurizer relief valve and steam generator safety valve shall not work, and (3) after the transients reactor systems shall become the steady state without manual adjustment of the reactor control system. The test results satisfied these criteria and some of test data showed that reactor had much more margin in any performance for design. It is verified, therefore, that the Mutsu reactor systems have adequate performances as a marine reactor and that one is capable to respond smoothly and safely to the load of ship's demand. (author)

  9. Development and application of nuclear power plant DCS closed-loop test platform

    International Nuclear Information System (INIS)

    A simulation platform with high flexibility and extensibility for nuclear power plant DCS closed loop test has been developed. The system modeling for Ling'ao Phase Ⅱ nuclear power plant has been built. Through an example of pressurizer pressure and water level control system testing under the condition of a 10% FP turbine power step-down, the way of using the platform for closed-loop DCS test and how to locate DCS problems were demonstrated. This test platform has been applied to DCS closed-loop test in Ling'ao Phase Ⅱ successfully. (authors)

  10. Time reversal tests in nuclear and neutron beta decay

    International Nuclear Information System (INIS)

    Motivation for time reversal violation studies in nuclear and neutron weak decay is discussed with an emphasis on searches for the exotic tensor and scalar weak interaction. The results of the experiment with polarized 8Li are updated. A new experiment with the aim to determine the transverse polarization of electrons emitted by free, polarized neutrons, is proposed. A facility for neutron decay studies with polarized cold neutrons is under construction at the spallation source SINQ-PSI

  11. Public decision and opinion - Nuclear energy and nuclear waste put to the test of democracy

    International Nuclear Information System (INIS)

    Some of the results of the opinion polls related to nuclear energy and nuclear waste, which were gathered in Western Europe as well as in the United States, are discussed here: can these converging results be of any help to decision-makers? Which lessons are to be learnt to consider new decision process which better meets the political realty at both the national and local levels? (authors)

  12. The rejection of the comprehensive nuclear test ban treaty by the US Senate: a reverse for the nuclear arms control?

    International Nuclear Information System (INIS)

    On October 13, 1999, after a hasty debate, the US Senate rejected the comprehensive nuclear test ban treaty (CTBT) signed 3 years ago. This article analyses this event with respect to the US domestic context (discussions at the Senate, reaction of the Presidency) and with respect to the international context (international reactions, future of the treaty, consequences on arms control policy). (J.S.)

  13. The Analysis of North Korea's Nuclear Tests by Turkish National Data Center

    Science.gov (United States)

    Semin, K.; Meral Ozel, N.; Destici, T. C.; Necmioglu, O.; Kocak, S.

    2013-12-01

    The Democratic People's Republic of Korea (DPRK) announced the conduct of a third underground nuclear test on 12 February 2013 in the northeastern part of the country as the previous tests that were conducted in 2009 and 2006. The latest nuclear test is the best detected nuclear event by the global seismic networks. The magnitude estimates show that each new test increased in size when compared with the previous one. As Turkish NDC (National Data Center), we have analyzed the 2013 and 2009 nuclear tests using seismic data from International Monitoring System (IMS) stations through the International Data Center (IDC) located in Vienna. Discrimination analysis was performed based on mb:Ms magnitude ratio and spectral analysis. We have also applied array based waveform cross-correlation to show the similarity of the nuclear tests and precise arrival time measurements for relative location estimates and basic infrasound analysis using two IMS infrasound stations for the 2013 event. Seismic analysis were performed using softwares such as Geotool, EP (Event processor from Norsar) and Seismic Analysis Code (SAC) and the infrasound data were analyzed by using PMCC from CEA-France. The IMS network is operating under the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The CTBTO verification system is under continuous development, also making use of the state of the art technologies and methodologies.

  14. OFFSITE ENVIRONMENTAL MONITORING REPORT: RADIATION MONITORING AROUND UNITED STATES NUCLEAR TEST AREAS, CALENDAR YEAR 1980

    Science.gov (United States)

    The U.S. Environmental Protection Agency's Environmental Monitoring Systems Laboratory in Las Vegas continued its Offsite Radiological Safety Program for the Nevada Test Site (NTS) and other sites of past underground nuclear tests. For each test, the Laboratory provided airborne ...

  15. PRELIMINARY GRAZING STUDIES WITH RUMEN-FISTULATED STEERS AT SELECTED NUCLEAR-TEST SITES

    Science.gov (United States)

    Rumen-fistulated steers (steers with a capped tube inserted into a permanent surgical opening into the stomach) were allowed to graze the fallout zones of six selected nuclear-test sites on the Nevada Test Site and Tonopah Test Range. Ingesta samples were analyzed for radionuclid...

  16. Welding of sule elements for nuclear reactors with solid state YAG laser using instrumentated testing equipments

    International Nuclear Information System (INIS)

    The instrumentation of the equipment for carrying out safety tests on fuel elements for nuclear reactors requires special thermocouples adapted to the prevailing agressive medium. The investigations described deal essentially with the operational and metallurgical weldability tests out on the safety test zircaloy piping in the pressurized water circuit (PHEBUS-programme)

  17. Testing for Nuclear Thermal Propulsion Systems: Identification of Technologies for Effluent Treatment in Test Facilities Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Develop a comprehensive understanding of requirements for a facility that could safely conduct effluent treatment for a Nuclear Thermal Propulsion (NTP) rocket...

  18. Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

    International Nuclear Information System (INIS)

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  19. United States Nuclear Tests, July 1945 through September 1992, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Nevada Operations Office

    2000-12-01

    This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

  20. Discrimination between earthquakes and underground nuclear explosions at Lopnor test site

    International Nuclear Information System (INIS)

    This paper evaluates, using different criteria, the effectiveness of discrimination between earthquakes and underground nuclear explosions at Lopnor test site. The records obtained from Talgar and Zerenda seismic arrays have been used for the present study. (author)

  1. 76 FR 52355 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report...

    Science.gov (United States)

    2011-08-22

    ...The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a document entitled: NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment,'' and subtitled ``Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants''. (Note that this document was......

  2. Preliminary nuclear design for test MOX Fuel rods

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Hyung Kook; Kim, Taek Kyum; Jeong, Hyung Guk; Noh, Jae Man; Cho, Jin Young; Kim, Young Il; Kim, Young Jin; Sohn, Dong Seong

    1997-10-01

    As a part of activity for future fuel development project, test MOX fuel rods are going to be loaded and irradiated in Halden reactor core as a KAERI`s joint international program with Paul Scherrer Institute (PSI). PSI will fabricate test MOX rods with attrition mill device which was developed by KAERI. The test fuel assembly rig contains three MOX rods and three inert matrix rods. One of three MOX rods will be fabricated by BNFL, the other two MOX fuel rods will be manufacturing jointly by KAERI and PSI. Three inert matrix fuel rods will be fabricated with Zr-Y-Er-Pu oxide. Neutronic evaluation was preliminarily performed for test fuel assembly suggested by PSI. The power distribution of test fuel rod in test fuel assembly was analyzed for various fuel rods position in assembly and the depletion characteristic curve for test fuel was also determined. The fuel rods position in test fuel assembly does not effect the rod power distribution, and the proposal for test fuel rods suggested by PSI is proved to be feasible. (author). 2 refs., 13 tabs., 16 figs.

  3. Benchmark Experiments at VNIITF Test Facilities for Verification of Nuclear Data Libraries

    International Nuclear Information System (INIS)

    The paper describes test facilities used by the Russian Federal Nuclear Center, All-Russian Institute of Technical Physics (VNIITF) to perform benchmark experiments essential for the verification of nuclear data libraries. The key experiments discussed in the paper include critical mass measurements; the investigation of reaction rate distribution in critical and subcritical systems, in particular those with a 14-MeV neutron source; and studies on the spectra of neutrons and gamma quanta emitted from spheres and reflected by hemispheres with a central pulse source of 14-MeV neutrons. New experiments are proposed with a view to revising nuclear data essential for new nuclear developments

  4. Data of ESR dosimetry study of population in the vicinity of Semipalatinsk Nuclear Test Site

    OpenAIRE

    Zhumadilov, Kassym; Ivannikov, Alexander; Stepanenko, Valeriy; Zharlyganova, Dinara; Zhumadilov, Zhaxybay; Apsalikov, Kazbek; Toyoda, Shin; Zhumadilova, Anara; Endo, Satoru; Tanaka, Kenichi; Miyazawa, Chuzou; Yamamoto, Masayoshi; Okamoto, Tetsuji; Hoshi, Masaharu

    2012-01-01

    The method of electron spin resonance (ESR) dosimetry was used to human tooth enamel to obtain individual absorbed doses of population of settlements in the vicinity of the Semipalatinsk Nuclear Test Site (SNTS), Kazakhstan. The distances between investigated settlements and Ground Zero (SNTS) are in the range 70 - 200 km from SNTS. Most of settlements (Dolon, Mostik, Bodene) are located near the central axis of radioactive fallout trace from the most contaminating surface nuclear test, which...

  5. Verification and Uncertainty Reduction of Amchitka Underground Nuclear Testing Models

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed Hassan; Jenny Chapman

    2006-02-01

    The modeling of Amchitka underground nuclear tests conducted in 2002 is verified and uncertainty in model input parameters, as well as predictions, has been reduced using newly collected data obtained by the summer 2004 field expedition of CRESP. Newly collected data that pertain to the groundwater model include magnetotelluric (MT) surveys conducted on the island to determine the subsurface salinity and porosity structure of the subsurface, and bathymetric surveys to determine the bathymetric maps of the areas offshore from the Long Shot and Cannikin Sites. Analysis and interpretation of the MT data yielded information on the location of the transition zone, and porosity profiles showing porosity values decaying with depth. These new data sets are used to verify the original model in terms of model parameters, model structure, and model output verification. In addition, by using the new data along with the existing data (chemistry and head data), the uncertainty in model input and output is decreased by conditioning on all the available data. A Markov Chain Monte Carlo (MCMC) approach is adapted for developing new input parameter distributions conditioned on prior knowledge and new data. The MCMC approach is a form of Bayesian conditioning that is constructed in such a way that it produces samples of the model parameters that eventually converge to a stationary posterior distribution. The Bayesian MCMC approach enhances probabilistic assessment. Instead of simply propagating uncertainty forward from input parameters into model predictions (i.e., traditional Monte Carlo approach), MCMC propagates uncertainty backward from data onto parameters, and then forward from parameters into predictions. Comparisons between new data and the original model, and conditioning on all available data using MCMC method, yield the following results and conclusions: (1) Model structure is verified at Long Shot and Cannikin where the high-resolution bathymetric data collected by CRESP

  6. Static and dynamic performance tests of nuclear powered ship Mutsu reactor (report on nuclear ship Mutsu power-up tests)

    Energy Technology Data Exchange (ETDEWEB)

    Ishida, Toshihisa; Kusunoki, Tsuyoshi; Ochiai, Masa-aki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tanaka, Yoshimi; Inoue, Kimio; Yao, Toshiaki; Kamai, Satoshi; Kitamura, Toshikatsu

    1992-08-01

    The power-up tests of the Mutsu reactor were performed from March 29th 1990 to December 14th. The tests were divided into six phases: The tests Phase 0 and Phase 1 were done in the state that the ship was moored at the quay of Sekinehama port in March and April; The tests Phase 2, Phase 3, Phase 4, and Phase 5 were done on the Pacific Ocean from July to December. Present report describes the test results on the static and dynamic plant performance. On static plant performance tests, there are 13 test items including measurements of primary system heat balance at low and high power levels, a virgin run of feed water pump with SG steam, a change-over test of steam supply of auxiliary boiler to SG. On the dynamic plant performance, there are 11 test items including a test of reactor power auto-control system, a test of main feed water auto-control system, a test of small load variation, a load increasing test, a turbine trip test, tests of ahead and astern maneuvering, a test of single loop operation, and a reactor scram test. The reactor power for each item`s test was increased step by step from zero power to the goal of rated power of 100 %, 36 MWt. In order to confirm proper reactor system performance, criteria were laid down for the static and dynamic tests: for example, (1) reactor scram shall not occur, (2) pressurizer relief valve and steam generator safety valve shall not work, and (3) after the transients reactor systems shall become the steady state without manual adjustment of the reactor control system. The test results satisfied these criteria and some of test data showed that reactor had much more margin in any performance for design. It is verified, therefore, that the Mutsu reactor systems have adequate performances as a marine reactor and that one is capable to respond smoothly and safely to the load of ship`s demand. (author).

  7. Static and dynamic performance tests of nuclear powered ship Mutsu reactor (report on nuclear ship Mutsu power-up tests)

    Energy Technology Data Exchange (ETDEWEB)

    Ishida, Toshihisa; Kusunoki, Tsuyoshi; Ochiai, Masa-aki (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Tanaka, Yoshimi; Inoue, Kimio; Yao, Toshiaki; Kamai, Satoshi; Kitamura, Toshikatsu.

    1992-08-01

    The power-up tests of the Mutsu reactor were performed from March 29th 1990 to December 14th. The tests were divided into six phases: The tests Phase 0 and Phase 1 were done in the state that the ship was moored at the quay of Sekinehama port in March and April; The tests Phase 2, Phase 3, Phase 4, and Phase 5 were done on the Pacific Ocean from July to December. Present report describes the test results on the static and dynamic plant performance. On static plant performance tests, there are 13 test items including measurements of primary system heat balance at low and high power levels, a virgin run of feed water pump with SG steam, a change-over test of steam supply of auxiliary boiler to SG. On the dynamic plant performance, there are 11 test items including a test of reactor power auto-control system, a test of main feed water auto-control system, a test of small load variation, a load increasing test, a turbine trip test, tests of ahead and astern maneuvering, a test of single loop operation, and a reactor scram test. The reactor power for each item's test was increased step by step from zero power to the goal of rated power of 100 %, 36 MWt. In order to confirm proper reactor system performance, criteria were laid down for the static and dynamic tests: for example, (1) reactor scram shall not occur, (2) pressurizer relief valve and steam generator safety valve shall not work, and (3) after the transients reactor systems shall become the steady state without manual adjustment of the reactor control system. The test results satisfied these criteria and some of test data showed that reactor had much more margin in any performance for design. It is verified, therefore, that the Mutsu reactor systems have adequate performances as a marine reactor and that one is capable to respond smoothly and safely to the load of ship's demand. (author).

  8. The international nuclear liability and compensation regime put to the test of a nuclear accident

    International Nuclear Information System (INIS)

    Full text: It appears that nuclear emergency plans place generally more emphasis on the nuclear safety and radiation protection aspects of the management of an accident, both inside the installation concerned and off-site, than on the particular requirements of local residents who would find themselves suddenly in such an emergency situation and of possible victims of nuclear damage. In a similar vein, studies focusing on the international nuclear third party liability regime usually take a global perspective and leave little room for the treatment of individual cases. The albeit welcome dearth of practical experience in Western countries in providing compensation for accidents of nuclear origin has, however, meant that public and local authorities are not always fully conscious of the importance of this question which should be dealt with in as practical a manner as possible. In order to cover all the legal and practical questions that could arise during the management of the consequences of a nuclear accident with regard to third party liability, insurance and compensation, the OECD/NEA held in co-operation with French authorities a workshop in November 2001. It was decided to organize this workshop according to three main stages: the alert phase, the accident phase and the post-accident phase; and to examine during these three stages the various roles played by local and national authorities, the nuclear operator and his insurer, as well as the nature and form of their respective actions. These questions were addressed both from the angle of applicable domestic legislation and of the relevant international conventions. From the analysis of different national experiences and of the information exchanged during the workshop, a striking diversity may be noted of solutions adopted or envisaged to address various aspects of civil liability, insurance and indemnification of damage in a nuclear emergency situation. This lack of uniformity should not necessarily be

  9. Significance of calibration explosions conducted at Semipalatinsk nuclear test site for the tasks of monitoring of nuclear explosions

    International Nuclear Information System (INIS)

    Signing of Comprehensive Nuclear Test Ban Treaty made the necessity of creating of monitoring systems over nuclear explosions most actual. This work is conducted in two directions. 1) Creation or modernization of existing seismic stations, included in the international monitoring system (IMS), according to specifications established in the documents of Preparatory Commission for the Comprehensive Nuclear Test Ban Treaty Organization. 2) Calibration of seismic stations. It's evident that calibration explosions are the most difficult stage in creation of monitoring network. For IMS stations to record rightly all corrections, information about explosions (coordinates, exact time of explosion, power, geological structure etc.) should be completely open. It imposes on the states declaring about calibration explosions increased obligations to reliability of the information. Calibration explosions, which are carried out at Semipalatinsk Nuclear Test Site, are the most interesting and most happy combination of work on liquidation of nuclear infrastructure of the site and development of IMS. These explosions have been conducted thanks to cooperation of two states: USA that finance realization of these operations and participate in scientific surveys and Kazakstan that manifest its good will in liquidation of a nuclear structure of the site and in consent to conduct calibration explosions, and ensuring an industrial part of works and geologic-geophysical measurements. By this time three explosions of 25 tons have been conducted in boreholes at the Balapan site and one explosion of 100 tons has been also conducted in the tunnel at the Degelen site. The results of their processing should contribute greatly both to calibration of seismic stations, and to development of identification methods of seismic events

  10. Seismic analysis and testing of nuclear power plants

    International Nuclear Information System (INIS)

    The following subjects are discussed in this guide: General Recommendations for seismic classification, loading combinations and allowable limits; seismic analysis methods; implications for seismic design; seismic testing and qualification; seismic instrumentation; modelling techniques; material property characterization; seismic response of soil deposits and earth structures; liquefaction and ground failure; slope stability; sloshing effects in water pools; qualification testing by means of the transport vehicle

  11. Introduction of Physical Protection Training and Test Facility of International Nuclear Nonproliferation and Security Academy

    International Nuclear Information System (INIS)

    International Nuclear Nonproliferation and Security Academy (INSA) aims to provide practical education and training programs, raise internationally-recognized experts, and improve awareness about nuclear nonproliferation and security. INSA will not only carry out wide variety of training courses but conduct various tests and develop technology in the field of nuclear nonproliferation and security by utilizing its SETT (Nuclear Security Training and Test facility). SETT will enable relevant industries and academia to come to the facility and conduct their own tests such as performance tests of newly developed products and equipment. Throughout this paper, the details of SETT such as configuration, each sector's purpose and deployed equipment will be described and explained particularly on the external physical protection training and test facility, which is called SETT/TB-I. The final approval by the national assembly is the only procedure left for the ROK government to pass the bill on the revised nuclear security and safety law. The revised law reflects most of the strengthened contents of INFCIRC/225/Revision5. When the new law comes into force, many extra efforts should be put into nuclear security area, specifically in the field of physical protection both on education/test and systematic performance-based evaluation. As stated above, SETT/TB-I has four sectors and each sector has specified purpose which differs from each others. For now, SETT/TB-I is considered having enough features to characterize the INSA and make it unique from other CoEs

  12. Fuel subassembly leak test chamber for a nuclear reactor

    International Nuclear Information System (INIS)

    A container with a valve at one end is inserted into a nuclear reactor coolant pool. Once in the pool, the valve is opened by a mechanical linkage. An individual fuel subassembly is lifted into the container by a gripper; the valve is then closed providing an isolated chamber for the subassembly. A vacuum is drawn on the chamber to encourage gaseous fission product leakage through any defects in the cladding of the fuel rods comprising the subassembly; this leakage may be detected by instrumentation, and the need for replacement of the assembly ascertained

  13. Peculiarities of vegetation restoration of low mountain massif 'Degelen' of Semipalatinsk Test Sites after nuclear tests

    International Nuclear Information System (INIS)

    Full text: Geo-botanical researches in low mountain massif 'Degelen' Semipalatinsk Test Site were conducted out in 1994-2000 in the frames of INTAS 93-1422 and INTAS 96-2072 projects. 209 underground nuclear explosions were conducted out in horizontal adits in granite low mountain massif in 1968-1989. At present PED γ-irradiation reaches 100-500 μR/h in 14 adits, 500-1000 μR/h - in 8 adits, 1000-5000 μR/h - in 5 adits. Crests of the main mountain ridges and their lateral spurs were destroyed by multiple influence of blasts of nuclear explosions. 'Zones of split' appeared at the tops of the mountain ridges. Technogene screens appeared on the slopes of the mountain ridges. Radioactive springs appeared as a result of opening of water-bearing horizons under nuclear explosions. 'Zones of split' consist of granite fragments measuring 0.1-3.0 meters. Higher plants were not revealed on ground with big rock fragments. Single individuals of Urtica wens, Setaria viridis are found on ground with small rock fragments. Rarefied aggregations constituted by Artemisia frigida, Festuca valesiaca, Agropyron cristatum develop in small depressions with accumulation of fine earth. Single individuals of petrophytes (Orostachys spinosa, Sedum hybridum, S. purpureum, Patrinia intermedia) appeared on small plots of slightly damaged areas of crests of the mountain ridges. Technogene screens are constituted by granite fragments measuring 0.03-1.0 meter. Higher plants were not found here. Only lower part of the screens sometimes is covered by shrubs - Rosa spinosissima, R. laxa, Spiraea trilobata, Lonicera microphylla, Berberis sibirica are found more rarely. Aggregations of weed plants (Artemisia scoparia, A. sieversiana, Amaranthus retroflexus) develop on orifice-side areas of the adits. We revealed development of adaptation signs of Melilotus albus and Kochia sieversiana growing in conditions of radiation pollution (PED of γ-irradiation 200-700 μR/h). Shape and dimensions of blade

  14. Non-Destructive Testing in Nuclear Technology Vol. I. Proceedings of a Symposium on Non-Destructive Testing in Nuclear Technology

    International Nuclear Information System (INIS)

    The Symposium on Non-Destructive Testing in Nuclear Technology was convened by the International Atomic Energy Agency and held, at the invitation of the Romanian People's Republic, in Bucharest from 17 to 21 May 1965. This was the first large IAEA symposium on this topic and was arranged with the help of the Romanian Institute of Atomic Physics. Over 100 participants from 20 countries and two international organizations presented 46 papers. The development of non-destructive testing techniques has increased considerably in recent years, particularly in the nuclear field. Nondestructive testing methods such as ultrasonic and radiographic testing are proving increasingly useful for ensuring that reactor materials and components will stand up to prolonged and rigorous use. Such methods are used to test for flaws, to check dimensions such as tube-wall thickness, and to determine the location and distribution of uranium fuel in a fuel element. Speakers stressed that these methods were invaluable for providing extensive and detailed data on the physical structure and condition of materials and the effects of fabrication processes. Among aspects of non-destructive testing that were discussed were the use of automation; assistance at the design stage for attaining higher strength-to-weight ratios; the testing of welds in reactor containment vessels; and the testing of sintered materials. The important information presented at the Symposium and the extensive discussions among scientists demonstrated the desire to accelerate solutions to various problems connected with non-destructive testing techniques

  15. Non-Destructive Testing in Nuclear Technology Vol. II. Proceedings of a Symposium on Non-Destructive Testing in Nuclear Technology

    International Nuclear Information System (INIS)

    The Symposium on Non-Destructive Testing in Nuclear Technology was convened by the International Atomic Energy Agency and held, at the invitation of the Romanian People's Republic, in Bucharest from 17 to 21 May 1965. This was the first large IAEA symposium on this topic and was arranged with the help of the Romanian Institute of Atomic Physics. Over 100 participants from 20 countries and two international organizations presented 46 papers. The development of non-destructive testing techniques has increased considerably in recent years, particularly in the nuclear field. Nondestructive testing methods such as ultrasonic and radiographic testing are proving increasingly useful for ensuring that reactor materials and components will stand up to prolonged and rigorous use. Such methods are used to test for flaws, to check dimensions such as tube-wall thickness, and to determine the location and distribution of uranium fuel in a fuel element. Speakers stressed that these methods were invaluable for providing extensive and detailed data on the physical structure and condition of materials and the effects of fabrication processes. Among aspects of non-destructive testing that were discussed were the use of automation; assistance at the design stage for attaining higher strength-to-weight ratios; the testing of welds in reactor containment vessels; and the testing of sintered materials. The important information presented at the Symposium and the extensive discussions among scientists demonstrated the desire to accelerate solutions to various problems connected with non-destructive testing techniques

  16. Verifying the nuclear-test ban. CTBTO: For a safer and more secure world [videorecording

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) was opened for signature in September 1996. In March 1997, the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization started work in Vienna, Austria. This film depicts the Commission's activities in establishing the Treaty's verification regime to monitor adherence to the global ban on nuclear explosions. It presents the challenging work at some of the global monitoring facilities, and at the International Data Centre in Vienna, where the data generated by the facilities are received, processed and analysed

  17. Some problems on the detection and the discrimination of the underground nuclear explosion test

    International Nuclear Information System (INIS)

    Most of people might think that the seismic observation network and its data would be useful for the detection and the discrimination of the underground nuclear explosion test. The difficulty on both the detection and the estimation of the event location would decrease when the seismic observation network would become denser, however, the difficulty on the discrimination of the event could not solve easily. Because the difficulty on the discrimination of the event is based on the difference between the characteristics of natural earthquake and underground nuclear explosion. In this paper, some problems on the detection and the discrimination of the underground nuclear explosion test are mentioned briefly. (author)

  18. Direct J-R curve analysis: application to testing of nuclear structural materials

    International Nuclear Information System (INIS)

    This paper deals with the application of the direct J-R curve methodology for the development of J-R curves for unirradiated and irradiated nuclear reactor structural materials. The load versus crosshead displacement data obtained during multi-specimen J testing of unirradiated carbon steels used for nuclear reactor piping applications and SS304 used in fast reactor applications, and unirradiated as well as irradiated nuclear pressure vessel steels (A533B) have been analysed and results reported. It was found that results from application of the direct J-R curve methodology resulted in less than 15% error as compared with the multi-specimen testing and analysis. (author)

  19. Prototype bellows sealed nuclear valve development -reliability through testing

    International Nuclear Information System (INIS)

    To assist in appraising bellows sealed valve performance, 10 tests were done on a ''1 in.'' prototype bellows sealed valve design. The tests simulated primary heat transport (PHT) system conditions for a 600 MWe CANDU-PHW. The design approach was to have all valve components outlast the bellows in endurance tests; this was achieved. The valve design meets the Atomic Energy of Canada Limited specification. For comparison, bellows fatigue failure data were fitted to both log-normal and Weibull distributions. A numerical example shows how to select valve stroke amplitude on the basis of valve flow requirement and the minimum acceptable fatigue life. (author)

  20. Spent nuclear fuel storage -- Performance tests and demonstrations

    International Nuclear Information System (INIS)

    This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report

  1. Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses.

  2. Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

    International Nuclear Information System (INIS)

    It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses

  3. Nuclear technology in materials testing and radiation protection

    International Nuclear Information System (INIS)

    A report of the 1974 activities of the laboratories for physical and measuring technical fundamentals, radiation effects and radiation protection, application of radionuclides and testing of radioactive materials of the Bundesanstalt fuer Materialpruefung (BAM) is given. (RW/LH)

  4. Nuclear EMP: stripline test method for measuring transfer impedance

    International Nuclear Information System (INIS)

    A method for measuring the transfer impedance of flat metal joints for frequencies to 100 MHz has been developed which makes use of striplines. The stripline method, which has similarities to the quadraxial method used for cylindrical components, is described and sets of test results are given. The transfer impedance of a simple joint is modeled as a spurious hyperbolic curve, and a close curve fit to transfer impedance test data from various samples is demonstrated for both the stripline and the quadraxial methods. Validity checks of the test data are discussed using the curve model and other criteria. The method was developed for testing riveted joints which form the avionics bays on B-1s. The joints must provide shielding from EMP currents

  5. Response time testing of temperature and pressure sensors in nuclear power plants

    International Nuclear Information System (INIS)

    Response time measurement tests are performed on most safety-related temperature and pressure sensors in a majority of the nuclear power plants in the United States. These tests, performed once every fuel cycle, insure that safety-related instrument channels will respond in a timely manner during design basis accidents. This paper provides a review of modern methods that are used for response time measurement, and example results from testing of temperature and pressure sensors in nuclear on-line testing at process operating conditions and thereby provide information about the actual in-situ performance of the sensors. These methods are referred to as the Loop Current Step Response (LCSR) test, which is used for response time testing of temperature sensors, and noise analysis test, which is used for response time testing of pressure, level and flow transmitters. (Author)

  6. Research on COC tests risk analysis method in CPR1000 nuclear power plant

    International Nuclear Information System (INIS)

    Power loss tests of I and C and meters power supply (COC) are the proper test for nuclear power plant commissioning. The purpose of this test is to demonstrate that, in the event of loss of the power, the plant can be maintained in hot shutdown conditions. Since the tests have high risks and are performed difficultly, any thoughtless risks might damage the equipment or unit. The article provides a new way as LBA example, which identifies risks from unit control and identifies system risks by loads breakdown structure, to solve risk analysis of COC test and insure the tests success. The tests performed successfully in LA Ⅱ nuclear power plant shows the analysis way can identify all-around the risk of COC tests, and it has high application value for CPR1000 commissioning. (authors)

  7. 'CANDU-fueling machine head tests' at the Institute for Nuclear Research - Pitesti

    International Nuclear Information System (INIS)

    The Fueling Machine (F/M) Head is the most complex equipment of the Fuel Handling System in the CANDU reactor and performs the change of the nuclear fuel during the reactor operation. Before the installation of the F/M Head at the Nuclear Power Plant, it was required to test its technical performances, to ensure that the equipment is ready for operation. Testing of the F/M Head at the Institute for Nuclear Research - Pitesti is a part of the overall program to assimilate in Romania the CANDU technology. There was an economic contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 untested. To perform testing of these machines at the Institute for Nuclear Research - Pitesti, a special testing rig was built and is available for this goal. Both the testing rig and staff have been successfully assessed by the AECL representatives during two visits, dated on December 2001 and March 2002. In 2003 the testing of the F/M Head no. 4 (RAM 5) was successfully completed. Today, in 2004, the functional test of the F/M Head no. 5 (RAM 6) is already performing. (authors)

  8. Results of a First Generation Propellant Energy Source Module Testing: Non-Nuclear Testing of Fission System

    Science.gov (United States)

    VanDyke, Melissa; Godfroy, Tom; Houts, Mike; Dickens, Ricky; Dobson, Chris; Pederson, Kevin; Reid, Bob

    1999-01-01

    The use of resistance heaters to simulate heat from fission allows extensive development of fission systems to be performed in non-nuclear test facilities, saving time and money. Resistance heated tests on the Module Unfueled Thermal- hydraulic Test (MUTT) article has been performed at the Marshall Space Flight Center. This paper discusses the results of these experiments to date, and describes the additional testing that will be performed. Recommendations related to the design of testable space fission power and propulsion systems are made.

  9. Equipment and piping for nuclear power plants, test and research reactors, and nuclear installations

    International Nuclear Information System (INIS)

    The standard concerns the primary and secondary circuits as well as the safety and protection equipment in nuclear power plants with PWR or LWGR type reactors. Rules for design, manufacturing, erection, operation, and maintenance of the reactors, steam generators, vessels, pumps and housings, and pressure pipes are provided

  10. Human errors in test and maintenance of nuclear power plants. Nordic project work

    International Nuclear Information System (INIS)

    The present report is a summary of the NKA/LIT-1 project performed for the period 1981-1985. The report summarizes work on human error influence in test and calibration activities in nuclear power plants, reviews problems regarding optimization of the test intervals, organization of test and maintenance activities, and the analysis of human error contribution to the overall risk in test and mainenace tasks. (author)

  11. Fallout Deposition in the Marshall Islands from Bikini and Enewetak Nuclear Weapons Tests

    OpenAIRE

    Beck, Harold L.; Bouville, André; Moroz, Brian E.; Simon, Steven L.

    2010-01-01

    Deposition densities (Bq m-2) of all important dose-contributing radionuclides occurring in nuclear weapons testing fallout from tests conducted at Bikini and Enewetak Atolls (1946-1958) have been estimated on a test-specific basis for all the 31 atolls and separate reef islands of the Marshall Islands. A complete review of various historical and contemporary data, as well as meteorological analysis, was used to make judgments regarding which tests deposited fallout in the Marshall Islands an...

  12. Yields of underground nuclear explosions at Azgir and Shagan River, USSR and implications for identifying decoupled nuclear testing in salt

    Energy Technology Data Exchange (ETDEWEB)

    Sykes, L.R.

    1991-12-05

    Bodywave magnitudes, mb, are recomputed using station corrections for all known Soviet underground nuclear explosions at Shagan River and Azgir. The mb values for explosions of announced yield, Y, in various parts of the world in either hard rock or below the water table were normalized to the SW part of the Shagan River testing area using previously published values of t* and mb bias. The resulting relationship, mb = 4.48 + 0.79 logY, which includes yields published by Bocharov et al. (1989) for Shagan River, differs very little from a regression that does not include those data. Using magnitudes determined from Lg at NORSAR as a standard, the Shagan River site is divided into three subareas. Yields calculated from these revised mb values and from m(Lg) are much more consistent for the same explosion; each agrees closely with the yields published by Bocharov et al. for large explosions in 1971 and 1972 in the NE and SW parts of the testing area. Yields calculated by averaging determinations from Lg and body waves for 66 explosions have a high precision at 95% confidence (mean value 1. 14) for Y > 10 kt. The explosion of 23 July 1973 of Y = 193 kt is clearly the largest underground explosion at Shagan River. The newly calculated values provide strong evidence of clustering in the distribution of yields of Soviet tests. In a special study yields of Soviet nuclear explosions, nuclear tests in salt, decoupling, evasion

  13. Development of TIG Welding System for a Nuclear Fuel Test Rig

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Changyoung; Ahn, Sungho; Hong, Jintae; Kim, Kahye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers.

  14. Development of TIG Welding System for a Nuclear Fuel Test Rig

    International Nuclear Information System (INIS)

    The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers

  15. Fabrication and Testing of Nuclear-Thermal Propulsion Ground Test Hardware Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Efficient nuclear-thermal propulsion requires heating a low molecular weight gas, typically hydrogen, to high temperature and expelling it through a nozzle. The...

  16. Method of testing fuel assemblies for nuclear reactors

    International Nuclear Information System (INIS)

    The stresses occurring in the fuel assemblies are simulated by power excursions. For this purpose the fuel assembly is placed in the neutron field of a test reactor and for a short time can be exposed to the much higher neutron field of a pulsed reactor. One possibility of design provides for the test and the pulsed reactor lying one above the other, separated by a neutron absorber and penetrated by a common irradiation channel. The fuel assembly then is to be moved from the position in the test reactor to the position in the pulsed reactor. The other possibility is to make the irradiation duct pass along the gap between both reactors and, by means of a tube-shaped absorber, open one or the other irradiation field. (DG)

  17. Rehabilitation of the former nuclear test sites at Maralinga

    International Nuclear Information System (INIS)

    The Department of Primary Industries and Energy, Canberra, has commenced tendering procedures for appointment of a Project Management Organisation for the Rehabilitation of the former British atomic weapon test sites at Maralinga and Emu in South Australia. This paper gives a historical background to the atomic tests, and reports scientific and engineering studies conducted by the Technical Assessment Group (TAG) to define practical and economic options for rehabilitation of the former test sites. The rehabilitation option preferred by the Australian Government will focus on removal and burial of soil and fragments highly contaminated with plutonium oxide, and erection of warning fences around areas where permanent residence will not be permitted. The application of in-situ vitrification is under investigation for stabilisation of twenty one disposal pits containing up to twenty kilograms of plutonium at Taranaki. 3 refs., 2 tabs., 3 figs

  18. Automatic testing technologies for I and C systems for nuclear power plants

    International Nuclear Information System (INIS)

    With the aim of enhancing the global competitiveness of instrumentation and control (I and C) systems for nuclear power plants, Toshiba has been making efforts to reduce the worker hours required for the testing of such systems and improve the quality of the tests. Display screen tests, which include many routine, repetitive tests and manual tests requiring a large number of operators to monitor multiple screen displays of the I and C system, are an essential element of the testing process. The introduction of automatic testing technologies is expected to substantially improve the efficiency of such display screen tests. We have now developed automatic testing technologies for display screen tests that can be applied without the need to change the I and C system. These technologies contribute to both the reduction of worker hours for testing and improvement of the quality of the tests. (author)

  19. Discussion on seismic test method for electrical equipment in nuclear power plant

    International Nuclear Information System (INIS)

    This paper describes the seismic test methods and requirements for electrical equipment in nuclear power plant. Advices and suggestions are provided based on the detail comparison and analysis of the international and national standards. It can be a reference for seismic testing engineers. (authors)

  20. Guideline to good practices for postmaintenance testing at DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Purpose of this guide is to provide contractor maintenance organizations with information that may be used for development and implementation of a postmaintenance testing process for structures, systems, and components at DOE nuclear facilities. It is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter 2, Element 9, Postmaintenance Testing.

  1. Site Earthquake Characteristics and Dynamic Parameter Test of Phase Ⅲ Qinshan Nuclear Power Engineering

    Institute of Scientific and Technical Information of China (English)

    ZHOV Nian-qing; ZHAO Zai-li; QIN Min

    2009-01-01

    The earthquake characteristics and geological structure of the site to sitting the Qinshan Nuclear Power Station are closely related. According to site investigation drilling, sampling, seismic sound logging wave test in single-hole and cross-hole, laboratory wave velocity test of intact rock, together with analysis of the site geological conditions, the seismic wave test results of the site between strata lithology and the geologic structure were studied. The relationships of seismic waves with the site lithology and the geologic structure were set up.The dynamic parameters of different grades of weathering profile were deduced. The results assist the seismic design of Phase Ⅲ Qinshan Nuclear Power Plant, China.

  2. Project of law relative to the sanitary consequences of French nuclear weapons tests

    International Nuclear Information System (INIS)

    In order to make easy the indemnifications and to include the persons having participate to nuclear weapons tests (Sahara and French Polynesia) and populations leaving in the concerned areas, the project of law relative to the repair of sanitary consequences of nuclear weapons tests proposes to create a right to integral repair of prejudices for the persons suffering of a radioinduced disease coming from these tests. The American example and the British example are given for comparison. The modalities of financing are detailed as well as the social economic and administrative impacts. (N.C.)

  3. Ionospheric response to the 25 May 2009 North Korean nuclear test

    Science.gov (United States)

    Chien, K.; Liu, J. G.

    2013-12-01

    An underground nuclear test may act a large artificial quake source on the Earth. Similar to earthquake perturbations, traveling ionosphere disturbances (TIDs) can be activated by nuclear tests. In this paper, we employed ground-based GPS receivers and an HF-CW (high frequency-continue wave) Doppler sounding system in Taiwan to detect the North Korean underground nuclear test on May 25, 2009. Remarkable TIDs in the GPS TEC (total electric content) and Doppler frequency shifts are observed 30-90 minutes after the test. The beam forming method is further applied to compute the TID speeds in the GPS TEC and Doppler shifts as well as find the location of the TID source.

  4. Radiation impact of nuclear weapons tests at the Semipalatinks test site on the population of the Altai region

    International Nuclear Information System (INIS)

    The population of the Altai region was exposed repeatedly to radiation during atmospheric tests of nuclear weapons from 1949 to 1962 and during cratering explosions in 1965. It has now been established that 22 nuclear explosions resulted in transport of radionuclides towards the Altai region. The nuclear explosions of 29 August 1949 alone produced an effective dose exceeding 250 mSv in 44 settlements. In the case of the nuclear explosion of 7 August 1962, the thyroid dose to persons living in a number of settlements was more than a few gray. The impact of the tests on the population of the Altai region has been under study since 1990 (as of 1992 under the ''Semipalatinsk test site/Altai'' State research programme). This study covers: reconstruction of doses from the tests, risk assessment, epidemiological studies, health and demosgraphic studies, and ecological research (radioactive and chemical contamination). The goals of the research are development and realization of the programme of additional measures for health protection and compensation, and environmental and social protection. The nuclear test of 1949 produced the greatest radiation impact. The total collective dose from this test to the population of the region is estimated at approximately 32,000 man·Sv, with about 250,000 individuals receiving a dose of above 5 cSv. The radiation impact from this test on the cohort and population levels was estimated using up-to-date scientific theories about stochastic health effects of ionizing radiation. The goal of the research is to obtain data on the consequences of the tests in order to plan social protection measures as well as future research. An analysis of the medico-ecological situation in the affected and control regions and an epidemiological study are being carried out. Some results of the study are presented in the paper. A concept of social protection for the population affected by the tests has been prepared and serves as the basis for taking

  5. Regional conflicts and nuclear fears

    International Nuclear Information System (INIS)

    The real danger of nuclear weapons in the Third World is not that developing countries will acquire them, but that advanced countries will intervene in Third World affairs with them. Nuclear weapons can play a part in Third World conflicts in two ways: a recognized nuclear weapon power can threaten to use the weapon in the conflict situation or a clandestine nuclear power may do so. In noting that most conflicts in the Third World can be sustained only through support from the developing countries, the author complains that the Non-Proliferation Treaty is pernicious because it legitimizes the use of nuclear weapons by a few weapon powers. He urges a two-step effort to pressure the North Atlantic Treaty Organization and the United Nations to make nuclear weapons illegal. 17 references

  6. 78 FR 58574 - Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants

    Science.gov (United States)

    2013-09-24

    ... COMMISSION Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power..., Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants.'' The guide... nuclear power plants. ADDRESSES: Please refer to Docket ID NRC-2013-0048 when contacting the NRC about...

  7. Polycythemia vera among participants of a nuclear weapons test

    Energy Technology Data Exchange (ETDEWEB)

    Sobell, J.L.; Codd, M.B.; Silverstein, M.N.; Kurland, L.T.

    1987-03-06

    Three letters-to-the-editors discuss the finding of a statistically significant excess of polycythemia vera cases among participants in the Smoky detonation. Had population-based incidence rates from Rochester been used to derive an expected incidence, and had only bona fide polycythemia vera cases been considered, as is the rule in most epidemiologic studies, the observed frequency of polycythemia vera among participants in the Smoky test would have been found to be well within chance expectations.

  8. A Hydrogen Containment Process for Nuclear Thermal Engine Ground testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    The objective of this study is to propose a new total hydrogen containment process to enable the testing required for NTP engine development. This H2 removal process comprises of two unit operations: an oxygen-rich burner and a shell-and-tube type of heat exchanger. This new process is demonstrated by simulation of the steady state operation of the engine firing at nominal conditions.

  9. Polycythemia vera among participants of a nuclear weapons test

    International Nuclear Information System (INIS)

    Three letters-to-the-editors discuss the finding of a statistically significant excess of polycythemia vera cases among participants in the Smoky detonation. Had population-based incidence rates from Rochester been used to derive an expected incidence, and had only bona fide polycythemia vera cases been considered, as is the rule in most epidemiologic studies, the observed frequency of polycythemia vera among participants in the Smoky test would have been found to be well within chance expectations

  10. Nuclear weapons testing fallout: proving causation for exposure injury

    International Nuclear Information System (INIS)

    A recent Federal District Court opinion dealing with exposure of civilians to fallout from atomic bomb testing more than two decades ago provides guidance on how court action may in the future, address this problem. Close to 1200 negligence liability claims have been brought against the US government in the names of individuals who had resided near the Nevada Test Site and who subsequently developed cancer or leukemia. Because of the importance and complexity of the cases, the parties involved mutually agreed to the selection of 24 bellwether cases which then provided a legal and factural pattern against which other cases may be subsequently matched. The trial court's decision announced in Allen vs. United States, concluded that the government had a duty to adequately monitor, warn, and educate the population put at risk by the tests and that it had failed to fulfill its duty. However, it is only through case-by-case decision making, by courts reviewing all of the evidence in specific cases and tailoring results to best fit the specific facts, that equitable solutions can be applied in our optimal number of cases

  11. Atmospheric nuclear tests of the 1950's and 1960's: A possible test of ozone depletion theories

    International Nuclear Information System (INIS)

    It will be shown that the model chemistries used to calculate the effects of supersonic transports for Climatic Impact Assessment Program and National Research Council studies and of large-scale nuclear exchanges for National Research Council studies cause our one-dimensional model to predict ozone depletions in 1963--1964 resulting from NO/sub x/ injected into the stratosphere by the atmosphere nuclear tests of 1956--1962 larger (4--14% ozone reduction in 1963) than is easily consistent with observation. However, calculations carried out with more recent model chemistries result in ozone reductions that are more easily consistent with observation

  12. Development of the instrumented capsule for nuclear fuel irradiation test at HANARO

    International Nuclear Information System (INIS)

    The instrumented capsule for the nuclear fuel irradiation test (hereinafter referred to as 'instrumented fuel capsule'), which is crucial for the verification of a nuclear fuel performance and safety, has been developed at HANARO (High-flux Advanced Neutron Application Reactor). The irradiation test of the first instrumented fuel capsule was carried out in March 2003 and the irradiation test of the second instrumented fuel capsule was carried out in April 2004 at HANARO. Through the irradiation tests of the two capsules, the design specifications and safety of the instrumented fuel capsule were successfully verified. In the first instrumented fuel capsule, only the technologies for measuring the center temperature of the nuclear fuel and neutron flux were implemented. In the second instrumented fuel capsule, the technologies for measuring the center temperature of the nuclear fuel, the internal pressure of the fuel rod, the elongation of the nuclear fuel and the neutron flux were implemented. Currently the dual instrumented technologies that alloy for two characteristics to be measured simultaneously in one fuel rod, is being developed. The duel instrumented fuel rods have been successfully designed as a part of the technology enhancement program for the instrumented fuel capsule. The instrumented fuel capsule will be utilized for the development of nuclear fuel. The instrumentation technologies for measuring the nuclear fuel characteristics will be applied to the 3-pin FTL (Fuel Test Loop) facility which is currently being developed. And, the duel instrumented technologies will contribute to enhancing the efficiency of the irradiation test using an instrumented fuel capsule at HANARO. (author)

  13. Research and project practice in AP1000 nuclear plant MCR assemblies seismic test

    International Nuclear Information System (INIS)

    Background: The seismic test is one of Plant Equipment Seismic Qualification Methodologies. Purpose: To satisfy the special requirements of AP1000 seismic qualification, this test is not same to traditional seismic test. Methods: AP1000 nuclear plant equipment qualification has new methods and requirements. The special requirements as response spectrum, accelerometer installation and functional test are described for AP1000 MCR seismic test. Results: The test results are demonstrated that MCR assemblies are satisfied as AP1000 seismic qualification requirements. Conclusions: These requirements are beneficial to the qualification for structural integrity and functional safety. They are also used to find design margin. (authors)

  14. Certification testing of safety relief valves for the nuclear power industry

    International Nuclear Information System (INIS)

    This paper presents a summary of current test methodology used to perform recertification testing of Code Safety Relief Valves (SRVs). This paper discusses current issues in SRV testing including the following: Alternate media testing including a discussion of EPRI Report NP-4235. In situ testing of SRVs using lift devices. Effects of handling and transportation on set point. SRV testing over the years at Wyle in close cooperation with the nuclear industry, NRC, and valve manufacturers provides the experience necessary to discuss lessons learned. These lessons may be helpful to those setting up inservice Inspection (ISI) Programs to effectively monitor SRV performance and meet the requirements of OM-1

  15. Measurement of anthropogenic radionuclides in the atmosphere with a radionuclide monitoring network for nuclear tests

    International Nuclear Information System (INIS)

    A worldwide radionuclide monitoring network for nuclear tests has detected the anthropogenic radioactive materials released in the atmosphere due to the accident of the Fukushima Daiichi Nuclear Power Plant impacted by the Great East Japan Earthquake on March 11, 2011. After four months have passed since the accident occurred, most overseas stations do not detect the radionuclides of Fukushima origin any more. The Takasaki station in Japan, however, is still detecting them every day. This paper describes radionuclide monitoring stations and the network of them as part of the International Monitoring System (IMS) in the Comprehensive Nuclear Test Ban Treaty (CTBT), as well as the measurement results of radionuclide particulates and radioactive isotopes of xenon released from the Fukushima Daiichi Nuclear Power Plant with the monitoring network. (J.P.N.)

  16. Nuclear Power Safety Reporting System implementation plan, concept evaluation and operability test

    International Nuclear Information System (INIS)

    During the 1984 fiscal year, the Aerospace Corporation continued to assist the US Nuclear Regulatory Commission (NRC) in evaluating the concept of a Nuclear Power Safety Reporting System (NPSRS). The NPSRS concept embodies a voluntary, nonpunitive, third party managed human factors data gathering system that (with the NRC as its parent agency) could be used for identifying and quantifying factors that contribute to the occurrence of safety problems involving personnel in nuclear power plants. NPSRS data could be used to: (1) support efforts to quantify the human reliability elements of probabilistic risk assessments (PRA's); (2) to evaluate the influence of various nuclear power plant systems on human error-proneness within the system; and (3) to aid in the development of design criteria for human-machine safety systems. The draft implementation plan and a description of the operability demonstration test have been published. Progress toward initiating the actual test is reported as are issues yet to be resolved

  17. Tests of time reversal invariance in nuclear physics

    International Nuclear Information System (INIS)

    The fundamental origin of CP violation has remained unclear for twenty-five years. A significant change in this situation occurred last year, however, with the announcement by a group (NA31) working at CERN of the first evidence of direct CP violation through a measurement of a non-zero value of ε '/ε reported to be (3.1 ± 1.1) x 10-3. This result is consistent with the range of values expected within the minimal standard model, described by the Kobayashi-Maskawa mass matrix for three generations. The result from a second experiment (E731) measuring this parameter at Fermilab appears from an analysis of part of the data set to be consistent with the CERN value but also consistent with zero, so that at this time, the non-zero nature of ε '/ε is not yet confirmed by a second experiment. If the minimal standard model is the correct picture, then it is unlikely that a violation of CP invariance due to weak interactions will be observed in anything but heavy quark systems. The electric dipole moment of the neutron, for example, is expected to be of the order of 10-31 e-cm in the standard model, owing to the fact that the violation arises as a second order weak effect. Current experiments are at the level of 10125 e-cm, or six orders of magnitude short of the prediction of the standard model. The neutron EDM and other T-violation signals in nuclear systems all acquire time reversal violation, within the standard model, as a second order weak effect. They are therefore more interesting as a search for physics beyond the standard model, where in some models effects appear in first order. One should bear in mind, however, that even within the standard model, there is the possibility of CP violation associated with the strong interaction θ parameter

  18. Action plan for the comprehensive nuclear-test-ban treaty (CTBT) Malaysian National Data Centre

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) is a keystone of the international regime on the non-proliferation of nuclear weapons and an essential basis for the pursuit of nuclear disarmament. Its total ban of any nuclear weapon test explosion moreover will restrict the development and qualitative improvement of nuclear weapons and end the development of advanced new types of these weapons. One of the key features of this treaty is the development of an International Monitoring System (IMS) to detect any nuclear weapon test. The IMS comprises a network of 321 monitoring stations and 16 radionuclide laboratories that monitor the Earth for evidence of nuclear explosions. It uses four verification methods, including seismic, hydroacoustic and infrasound, in addition to radionuclide monitoring of the underground, underwater and atmosphere environments, respectively, whereas, radionuclide monitoring can detect radioactive debris vented from atmospheric, underground or underwater nuclear explosions. Malaysia signed the CTBT on 23 July 1998, and is currently in the process of drafting a national CTBT Act to facilitate ratification. As provided for under the Treaty, one of the radionuclide-monitoring stations (Rain) under the IMS will be located in Malaysia. The station is under the responsibility of the Malaysian Nuclear Agency, as the National Authority for the CTBT. The operation of the IMS is supported by an International Data Centre (IDC) CTBT, which is based at the headquarters of the Preparatory Commission for the CTBT Organization (CTBTO) in Vienna. To facilitate the acquisition of data from the IMS for the purposes of verifying compliance with the Treaty in general, and to enable Malaysia to benefit from the scientific applications of the data obtainable from the IDC, a CTBT National Data Centre (NDC) is the process of being established in Malaysia , which is targeted to be fully operational by the third quarter of 2007. (Author)

  19. Non-destructive testing dummy nuclear fuel rods by neutron radiography

    International Nuclear Information System (INIS)

    Background: The nuclear fuel rod is a key component of nuclear plants and reactors. It works in the extreme conditions, so it is easy to be broken. In order to be safe in operation, lots of testings have to be carried out from fabricating to operating of the fuel rod. Purpose: As a unique non-destructive testing technique, neutron radiography can be used to measure the nuclear fuel rods with radioactivity by an indirect neutron radiography method. Study the indirect neutron radiography method is the primary step of testing. Methods: Non-destructive testing experiments were carried out at China Advanced Research Reactor (CARR) by indirect neutron radiography method with dummy nuclear fuel rods as the samples. The 0.1 mm-thick Dy foil was used as the neutron converter. Results: The neutron images of dummy nuclear fuel rods were obtained. The resolution of testing was analyzed with the images. Through imaging analysis methods, the structure defections, the hydrogen accumulation in the cladding and the U-235 enrichment of pellet were studied and analyzed. Conclusions: The indirect neutron radiography method and the neutron image analysis method were studied. The work described in this paper provides a primary guideline for investigating actual irradiated fuel rods by the neutron radiography at CARR in the future. (authors)

  20. Seismic qualification tests of safety-related valves and air dampers for nuclear power plants (active components test program)

    International Nuclear Information System (INIS)

    In nuclear power plants there are many safety-related valves and air dampers required to operate under earthquakes. They have moving parts or actuators such as driving motors and disks. Selecting typical eighteen valves and two air dampers used in BWR and PWR plants in Japan, a series of vibration tests, which was one of the 'Active Components Test Program' study, were carried out to prove seismic quality. This paper summarizes these test results. Typical eighteen valves and two air dampers were selected for vibration tests. Maximum response acceleration achieved in vibration tests were three to eight G at the valve actuators. Any safety matter problems were not found in vibration tests. An analytical model of valves for piping analysis was also verified in this study. (orig.)

  1. Geology of the Chinese nuclear test site near Lop Nor, Xinjiang Uygur Autonomous Region, China

    Science.gov (United States)

    Matzko, J.R.

    1994-01-01

    The Chinese underground nuclear test site in the Kuruktag and Kyzyltag mountains of the Xinjiang Uygur Autonomous Region of northwest China, is the location of sixteen underground tests that occurred between 1969 and 1992. The largest test to date, conducted on 21 May 1992, had a reported yield of about one megaton. Geophysical properties of the rocks and a large-scale geologic map of part of the test area were published by the Chinese in 1986 and 1987 and are the first site-specific data available for this test site. In areas of low relief, underground nuclear testing has occurred below the water table, in shafts drilled vertically into dense, low porosity Paleozoic granitic and metasedimentary rocks. Additional testing in areas of more rugged terrain has occurred in horizontal tunnels, probably above the water table. At least one of these tunnels was driven into granite. The upper 50 m of the rock in the area of the vertical tests is weathered and fractured; these conditions have been shown to influence the magnitude of the disturbance of the land surface after a nuclear explosion. These descriptions suggest hard rock coupling at depth and a closer resemblance to the former Soviet test site in eastern Kazakhstan than to the U.S. test site in Nevada. ?? 1994.

  2. Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report

    Energy Technology Data Exchange (ETDEWEB)

    Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

    1998-07-01

    Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

  3. Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report

    International Nuclear Information System (INIS)

    Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA

  4. Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; John D. Bess; Jim Gulliford; Ian Hill

    2013-10-01

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the nuclear data community at ND2007. Since ND2007, integral benchmark data that are available for nuclear data testing have increased significantly. The status of the ICSBEP and the IRPhEP is discussed and selected benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2007 are highlighted.

  5. Effect of Induced Refractive Error and Nuclear Sclerotic Cataracts on Ishihara Colour Plate Testing

    OpenAIRE

    Eneh AA; Rogalska T; Urton T; Schweitzer KD

    2014-01-01

    Objective: To determine the effect of induced refractive blur and nuclear sclerotic (NS) cataracts on Ishihara colour plate (ICP) scores. Design: Prospective evaluation of a diagnostic test Participants: Patients who presented to Hotel Dieu Hospital Eye clinic between January and March 2010 with either a lone diagnosis of nuclear sclerotic cataracts, or with no identified ocular disease with complete examination. Methods: Patients were divided into two groups: those having no id...

  6. Nuclear Propulsion and Power Non-Nuclear Test Facility (NP2NTF): Preliminary Analysis and Feasibility Assessment Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Nuclear reactors, which power nuclear propulsion and power systems, and the nuclear radiation and residual radioactivity associated with these systems, impose...

  7. Experiences with the test facility MILLI for reprocessing nuclear fuel

    International Nuclear Information System (INIS)

    The facility MILLI is designed for experiments on dissolution and extraction of highly irradiated fuels with any enrichment. MILLI was designed and constructed from 1965 to 1970. After cold tests in 1971 the facility has been in hot operation since that time. Experiences with the reprocessing of high-burned UO2- and (U, Pu)O2-LWR and (U, Pu)O2-FBR fuel have been gained and have found application in the Karlsruhe reprocessing plant (WAK) as well as in the conceptual design of the large reprocessing plant in Gorleben. (orig.)

  8. Testing of reactor fuel materials using nuclear techniques

    International Nuclear Information System (INIS)

    The tests presented here apply to: the quantitative determination of uranium in the core of fuel element plates by the detection of the number of neutrons produced in photo induced reactions in uranium; the determination of 235U proportion in uranium dioxide samples, in the form of uranyl nitrate, by the technique of the detection of tracks produced by fission fragments and in pellet samples by passive gamma spectrometry and the checking of uranium homogenization distribution in fuel plates and uranium dioxide pellets. (Author)

  9. Shaking table test study on seismic performance of dehydrogenation fan for nuclear power plants

    International Nuclear Information System (INIS)

    Seismic performance of the dehydrogenation fan for nuclear power plants was evaluated based on the shaking table test of earthquake simulation. Dynamic characteristics including the orthogonal tri-axial fundamental frequencies and equivalent damping ratios were measured by the white noise scanning method. Artificial seismic waves were generated corresponding to the floor acceleration response spectra for nuclear power plants. Furthermore, five OBE and one SSE shaking table tests for dehydrogenation fan were performed by using the artificial seismic waves as the seismic inputs along the orthogonal axis simultaneity. Operating function of dehydrogenation fan was monitored and observed during all seismic tests, and performance indexes of dehydrogenation fan were compared before and after seismic tests. The results show that the structural integrity and operating function of the dehydrogenation fan are perfect during all seismic tests; and the performance indexes of the dehydrogenation fan can remain consistent before and after seismic tests; the seismic performance of the dehydrogenation fan can satisfy relevant technical requirements. (authors)

  10. The advanced test reactor national scientific user facility: advancing nuclear technology education

    International Nuclear Information System (INIS)

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy designated the Idaho National Laboratory (INL) Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The ATR NSUF provides education programs including a Users Week, internships, faculty student team projects and faculty/staff exchanges. In addition, the ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  11. IAEA Preliminary Assessment of the Former French Nuclear Test Sites in Algeria

    International Nuclear Information System (INIS)

    In 1999, the International Atomic Energy Agency received a request from the Government of Algeria to perform an assessment of the radiological conditions of the former sites used by the French Government in the early 1960s for the testing of nuclear weapons. This paper describes the history and the nature of the test site and the tests that were performed, the methodology of the IAEA assessment and the results and conclusions drawn from the mission of international experts. (author)

  12. Evaluation of the natural circulation capability test results for Ulchin nuclear power plant unit 3

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Kang Sik; Jeong, Weon Sang; Lee, Ju Han; Seo, Jong Tae; Lee, Sang Keun [Korea Power Engineering Company, Inc., Taejon (Korea, Republic of); Mo, Yong Won; Ryuk, Keun Su; Shin, Bong Chul; Kim, Byung Ho; Oh, Chul Sung [KEPCO, Ulchin (Korea, Republic of)

    1998-10-01

    During the Power Ascension Test (PAT) period, the transient tests related to the natural circulation capability were successfully completed for Ulchin Nuclear Power Plant Unit 3 (UCN 3). The tests were successfully completed by meeting all acceptance criteria. The post-trip PCS shows good performance as designed and the measured natural circulation capacity was demonstrated to be adequate for the core decay heat removal for UCN 3.

  13. Testing of advance design types of instrument current transformers for Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Current transformers designed and produced in IVEP Brno for the measurement of electric energy, for control and protection of the generator-transformer unit of the Temelin nuclear power plant are described. Presented are tests performed according to the standard test CSN 35 1360 and CSN 35 1361 as well as tests respecting a revision of these standards according to IEC 185. (author) 1 tab., 2 figs., 7 refs

  14. Evaluation of the natural circulation capability test results for Ulchin nuclear power plant unit 3

    International Nuclear Information System (INIS)

    During the Power Ascension Test (PAT) period, the transient tests related to the natural circulation capability were successfully completed for Ulchin Nuclear Power Plant Unit 3 (UCN 3). The tests were successfully completed by meeting all acceptance criteria. The post-trip PCS shows good performance as designed and the measured natural circulation capacity was demonstrated to be adequate for the core decay heat removal for UCN 3

  15. Chemical Explosion Experiments to Improve Nuclear Test Monitoring - Developing a New Paradigm for Nuclear Test Monitoring with the Source Physics Experiments (SPE)

    International Nuclear Information System (INIS)

    A series of chemical explosions, called the Source Physics Experiments (SPE), is being conducted under the auspices of the U.S. Department of Energy's National Nuclear Security Administration (NNSA) to develop a new more physics-based paradigm for nuclear test monitoring. Currently, monitoring relies on semi-empirical models to discriminate explosions from earthquakes and to estimate key parameters such as yield. While these models have been highly successful monitoring established test sites, there is concern that future tests could occur in media and at scale depths of burial outside of our empirical experience. This is highlighted by North Korean tests, which exhibit poor performance of a reliable discriminant, mb:Ms (Selby et al., 2012), possibly due to source emplacement and differences in seismic responses for nascent and established test sites. The goal of SPE is to replace these semi-empirical relationships with numerical techniques grounded in a physical basis and thus applicable to any geologic setting or depth

  16. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    Energy Technology Data Exchange (ETDEWEB)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

    1982-08-01

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

  17. Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dunlop, A.; Colaccino, J.

    1996-12-01

    Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

  18. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    International Nuclear Information System (INIS)

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years

  19. Characteristics of acoustic wave from atmospheric nuclear explosions conducted at the USSR Test Sites

    Science.gov (United States)

    Sokolova, Inna

    2015-04-01

    Availability of the acoustic wave on the record of microbarograph is one of discriminate signs of atmospheric (surface layer of atmosphere) and contact explosions. Nowadays there is large number of air wave records from chemical explosions recorded by the IMS infrasound stations installed during recent decade. But there is small number of air wave records from nuclear explosions as air and contact nuclear explosions had been conducted since 1945 to 1962, before the Limited Test Ban Treaty was signed in 1963 (the treaty banning nuclear weapon tests in the atmosphere, in outer space and under water) by the Great Britain, USSR and USA. That time there was small number of installed microbarographs. First infrasound stations in the USSR appeared in 1954, and by the moment of the USSR collapse the network consisted of 25 infrasound stations, 3 of which were located on Kazakhstan territory - in Kurchatov (East Kazakhstan), in Borovoye Observatory (North Kazakhstan) and Talgar Observatory (Northern Tien Shan). The microbarograph of Talgar Observatory was installed in 1962 and recorded large number of air nuclear explosions conducted at Semipalatinsk Test Site and Novaya Zemlya Test Site. The epicentral distance to the STS was ~700 km, and to Novaya Zemlya Test Site ~3500 km. The historical analog records of the microbarograph were analyzed on the availability of the acoustic wave. The selected records were digitized, the database of acoustic signals from nuclear explosions was created. In addition, acoustic signals from atmospheric nuclear explosions conducted at the USSR Test Sites were recorded by analogue broadband seismic stations at wide range of epicentral distances, 300-3600 km. These signals coincide well by its form and spectral content with records of microbarographs and can be used for monitoring tasks and discrimination in places where infrasound observations are absent. Nuclear explosions which records contained acoustic wave were from 0.03 to 30 kt yield for

  20. Minisatellite mutations and retrospective biodosimetry of population living close to the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    During the period between 1949 and 1989 nuclear weapon testing carried out at the Semipalatinsk Nuclear Test Site (STS) resulted in local fallout affecting the residents of Semipalatinsk, East Kazakhstan and Pavlodar districts of Kazakhstan and Altai region of Russia. The Semipalatinsk nuclear polygon in Kazakhstan has been the site for 470 nuclear tests, including 26 tests performed on the ground and 87 in the atmosphere. More than 1.5 million people living in the vicinity of the test site were repeatedly exposed to ionizing radiation. The paper reviews the study where the main objectives are: (1) to establish a biosample database of blood samples of families in three generations living close to the STS and control families in three generations from clean areas, (2) to determine the minisatellite mutation rates in the three generations of exposed people and the control families of the same ethinic origin living in non-contaminated areas, and (3) to determine the chromosomal translocation frequencies by FISH chromosome painting in the lymphocytes of the exposed and the control people in order to determine the radiation exposure. The aim of the study was to select the population living near to the STS and subjected to the greatest radiation exposure. Of particular interest was the first test of 29th of August 1949, as this was reported to have caused heavy fallout along a narrow trajectory extending north-east from Polygon, also covering parts of the Altai region of Russia and parts of Pavlodar and Karaganda regions in Kazakhstan

  1. Tests of qualification of national components of nuclear power plants under design basis accident

    International Nuclear Information System (INIS)

    With the purpose of qualifying national components of nuclear power plants, whose working must be maintained during and after an accident, the Thermohydraulic Division of CDTN have done tests to check the equipment stability, under Design Basis Accident conditions. Until this moment, the following components were tested: electrical junction boxes (connectors); coating systems for wall, inside cover and steel containment; hydraulics components of personnel and equipment airlock. This work describes the test instalation, the tests performed and its results. The components tested, in a general way, fulfil the specified requirements. (author)

  2. Historical sketches of Sandia National Laboratories nuclear field testing. Volume 1: Full discussion except for sensitive references

    International Nuclear Information System (INIS)

    This report contains historical sketches that cover the major activities of Sandia nuclear field testing, from early atmospheric shots until 1990. It includes a chronological overview followed by more complete discussions of atmospheric, high-altitude, underwater, cratering, and underground nuclear testing. Other activities related to nuclear testing and high-explosive tests are also described. A large number of references are cited for readers who wish to learn more about technical details. Appendices, written by several authors, provide more insight for a variety of special aspects of nuclear testing and related work. Two versions of this history were published: volume 1 has an unlimited distribution, and volume 2 has a limited distribution

  3. Reinforced evidence of a low-yield nuclear test in North Korea on 11 May 2010

    International Nuclear Information System (INIS)

    In May 2010 unique aerosol-bound and noble gas (xenon) radionuclide signatures were observed at four East Asian surveillance stations designed to detect evidence of nuclear testing. An article published in early 2012 provided an analysis that suggested the findings were due to a low-yield underground nuclear test in North Korea on 11 May 2010. As the aerosol and noble gas datings, however, only agreed on the fringes of their uncertainties an official North Korean telegram that on 12 May 2010 reported about a nuclear fusion experiment 1 month earlier inspired a solution. Assuming that included a low-yield nuclear explosion and that it had left xenon isotopes in the same cavity, the xenon dating could be 'moved' to overlap with the aerosol dating. The article stirred a serious controversy where representatives of the U.S. government and the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) refused to comment on it. In this paper the xenon dating agrees with the aerosol one without resorting to a previous explosion. It shows instead that fractionation during lava cooling is the explanation and how that plays a paramount role in how xenon signatures from underground nuclear explosions should be interpreted. It also presents new observations that effectively imply that no nuclear reactor or any other nuclear installation could have caused the May 2010 signals. All in all these are the most interesting and rich ones ever encountered by the Organization and they truly demonstrate that the verification system can deliver much better sensitivity than it was originally designed for. (author)

  4. Constraints on the Required Number of Debris for the Nuclear Fuel Debris Trapping Efficiency Test

    International Nuclear Information System (INIS)

    It is reported that the percentage of the debris-induced fuel failure covers more than 35% for BWRs. Since debris is produced during nuclear power plant construction or overhaul period, types of debris may be dependent upon plant environment and systems. Debris that can generate the fuel failure is mostly metals having various shapes. Nuclear fuel vendors have their own test facilities for evaluating debris-filtering efficiency of nuclear fuels but every fuel vendor may seem to employ its own debris types for debris-filtering tests. In addition, its test method along with its test facility is different one another. To protect fuels from debris, fuel vendors including KEPCO NF (KEPCO Nuclear Fuel) provide the fuel with debris filtering capacity. During the fuel development process, debris filtering test is usually performed for filtering efficiency measurement. This paper discusses the required number of debris specimens for confident test results considering the constraints such as geometry, significance level, and economy. Debris induced fuel failure is one of major failure mechanism in the nuclear fuel. Therefore, the filtering capability should be implemented in the fuel. Debris filtering performance can be measured through a debris filtering test. In this paper, the constraints on the number of debris specimens was discussed. To guarantee independent filtering event for a specific debris, one must minimize the interference between themselves during the test. In addition, to acquire confident evaluation result, one must use lots of specimens. Trade-off of the two concepts was the motivation of the work. Thus, the authors developed a guidance to determine moderate number of specimen. Some of their work is still being verified, and their final work will also be reported

  5. Design Feature and Prototype Testing Methodology of DHIC's Nuclear I and C System

    International Nuclear Information System (INIS)

    The DHIC has developed an I and C system for a nuclear power plant through a Korean Government R and D project since 2001. This I and C system was designed and implemented to be applied for the new 1400MW nuclear power plant of KHNP. This system's design is based on the class-1E PLC platform and the non-class1E DCS platform. The PPS, the ESF-CCS, the RCOPS, the QIAS-P/N, the PCS, the NPCS, the P-CCS and the NIMS were designed, implemented and tested. The R and D project has been developed under a systematic and guided QA plan, but it is not easy to be applied for a new NPP such as Shin-Ulchin 1 and 2. To resolve problems of the first-application concerns, a new idea of integrated performance testing was adopted. A main control room for a verification test facility was constructed and it has features of a compact, video-based man-machine interface. The MCR includes five operation consoles, a Large Display Panel. A test system for a verification test facility is implemented as similar as a control and protection system of SUN 1 and 2. Integration level tests such as a system test, an interface test, a MMI test, a system function/performance test, a failure mode test, a response time test, a network load test, an alarm test, a reactor power cutback system test, an unit load transient test and a scenario test were performed using the prototype test facilities. These kinds of testing can verify and pre-validate the integrated I and C system's performance and flexibility. It could offer an implementation training before construction and also minimize trial errors to be found in the site. (author)

  6. Welding process optimization of nuclear fuel rod using TIG technique for fuel irradiation tests

    International Nuclear Information System (INIS)

    The irradiation test of fuel elements was planned for the evaluation of nuclear fuel performance. To establish fabrication process satisfying the requirements of irradiation test, orbital-TIG welding system for fuel elements was developed, and preliminary welding experiments for optimizing process conditions of fuel element was performed. Fuel elements with 9.5mm diameter and 0.6mm wall thickness of cladding tubes and end caps have been used and optimum conditions of endcap welding have been selected. In this study, the qualification test was performed by tensile tests, helium leak inspections, and metallography examinations to qualify the end cap welding procedure. The soundness of the welds quality of nuclear fuel elements has been confirmed by mechanical tests and microstructural examinations

  7. Refurbish research and test reactors corresponding to global age of nuclear energy

    International Nuclear Information System (INIS)

    This special article featured arguments for refurbishment of research and test reactors corresponding to global age of nuclear energy, based on the report: 'Investigation of research facilities necessary for future joint usage' issued by the special committee of Atomic Energy Society of Japan (AESJ) in September 2010. It consisted of six papers titled as 'Introduction-establishment of AESJ special committee for investigation', 'State of research and test reactors in Japan', 'State of overseas research and test reactors', 'Needs analysis for research and test reactors', 'Proposal of AESJ special committee' and 'Summary and future issues'. In order to develop human resources and promote research and development needed in global age of nuclear energy, research and test reactors would be refurbished as an Asian regional center of excellence. (T. Tanaka)

  8. Study of evaluation techniques of software testing and V and V in Nuclear Power Plants

    International Nuclear Information System (INIS)

    The study of activities to solve software safety and quality must be executed in base of establishing software development process for digitalized nuclear plant. Especially study of software testing and verification and validation must executed. For this purpose methodologies and tools which can improve software qualities are evaluated and software testing and V and V which can be applied to software life cycle are investigated. This study establish a guideline that can assure software safety and reliability requirements in digitalized nuclear plant systems and can be used as a guidebook of software development process to assure software quality many software development organization

  9. Data of the 22nd nuclear explosion test of the People's Republic of China

    International Nuclear Information System (INIS)

    US. Energy Research and Development Administration (US ERDA) announced for the 22 nd nuclear explosion test of the People's Republic of China. The radioactivity surveillance was carried out for the period from September 19, to September 28, 1977. From the results of this surveillance, the effects of this nuclear explosion test were detected in the radioactivity measurement of rainwater, dry fallout, air-borne dusts in upper atmosphere, and raw milk samples. Survey on iodine-131 concentrations in raw milk was continued until October 11, 1977. The results of radioactivity surveillance were described in the following articles. (author)

  10. Nuclear tests: the late indemnification of victims; Essais nucleaire: l'indemnisation tardive des victimes

    Energy Technology Data Exchange (ETDEWEB)

    Charbonneau, S. [Bordeaux-1 Univ., 33 (France)

    2010-04-15

    The author briefly recalls the historical context of the creation of the CEA and outlines the silence and denial about the radioactive contamination of military personnel during the nuclear tests performed in the Algerian Sahara and in Polynesia. He also outlines the continuous action of the association of veterans and victims of these nuclear tests which gathered proofs of health consequences. He comments the content and scope of application of laws which have been lately adopted (in 2010) to acknowledge these facts and indemnify the victims

  11. Radionuclide observables during the Integrated Field Exercise of the Comprehensive Nuclear-Test-Ban Treaty

    Energy Technology Data Exchange (ETDEWEB)

    Burnett, Jonathan L.; Miley, Harry S.; Milbrath, Brian D.

    2016-01-05

    In 2014 the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) undertook the Integrated Field Exercise (IFE) in Jordan. The exercise consisted of a simulated 0.5 – 2 kT underground explosion triggering an On-site Inspection (OSI) to search for evidence of a Treaty violation. This research evaluates two of the OSI techniques, including laboratory-based gamma-spectrometry of soil samples and in situ gamma-spectrometry for 17 particulate radionuclides indicative of nuclear weapon tests. The detection sensitivity is evaluated using real IFE and model data. It indicates that higher sensitivity laboratory measurements are the optimum technique during the IFE and OSI timeframes.

  12. Mortality and cancer incidence in UK participants in UK atmospheric nuclear weapon tests and experimental programmes

    International Nuclear Information System (INIS)

    A brief report is given of a study by the NRPB on the mortality and cancer incidence in UK participants in UK atmospheric nuclear weapon tests and experimental programmes. The results of 22,347 participants were compared with a population of 22,326 controls. It was concluded that participation in the nuclear weapons tests had no detectable effect on the participants' expectation of life or on their total risk of developing cancer, apart possibly from an effect on the risks from developing multiple myeloma and leukaemia. (U.K.)

  13. Aspects and features of the effects of Chinese nuclear explosion tests

    International Nuclear Information System (INIS)

    This paper documents the characteristics of the environmental effects of Chinese nuclear explosion tests done during 1973-1980, measured by Ge semiconductor detectors in Fukui prefecture, a coastal area faced to Japan Sea. The earlier explosions 1960's and 1970's are also taken into considerations. Fukui prefecture has reported all these investigation results and provided information especially on radionuclide analysis results. In this review paper, fallout amounts of days to years living radioactive nuclides, maximum and average concentration values for each environmental materials examined, and evaluation of internal and external radiation doses are presented in tables, thus aspects and features of Chinese nuclear explosion tests are described. (S. Ohno)

  14. Data of the 21st nuclear explosion test of the People's Republic of China

    International Nuclear Information System (INIS)

    The news of Kyodo-Reuter said that on 17 November 1976 the Energy Research and Development Administration (ERDA), U.S.A., announced for the 21st nuclear explosion test of the People's Republic of China. The radioactivity surveillance was carried out for the period from 18 November 1976 to 25 November 1976. From the results of the surveillance, a few effects of this nuclear explosion test were detected in the radioactivity measurement of rain, dry fallout, and air-borne dust. (author)

  15. Cytogenetic survey of people from the region of Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    The results of cytogenetic examination of people from the region of Semipalatinsk nuclear test site (the village Sarzhal). The frequency spectrum and the ratio of different types of chromosomal aberrations in the examined persons living in the most contaminated areas, confirm the deleterious mutagenic effects of ionizing radiation on chromosomes of the population in the studied group compared to controls. The high variability in the frequency of chromosomal aberrations - from 0 to 8% of the people and the lack of connection with the epidemiological data indicates heterogeneity of the population by radiosensitivity. Key words: chromosomal aberrations, radiosensitivity, ionizing radiation, biodosimetry, Semipalatinsk nuclear test site

  16. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

  17. Compaction comparison testing using a modified impact soil tester and nuclear density gauge

    International Nuclear Information System (INIS)

    The purpose of this paper is to compare test results of a modified Impact Soil Tester (IST) on compacted soil with data obtained from the same soil using a nuclear density gauge at the US Army Corp of Engineer's Buena Vista Flood Wall project in Buena Vista, Virginia. The tests were run during construction of the earth flood wall during the summer of 1996. This comparison testing demonstrated the credibility of the procedure developed for the IST as a compacting testing device. The comparison data was obtained on a variety of soils ranging from silty sands to clays. The Flood Wall comparison compaction data for 90% Standard Proctor shows that the results of the IST as modified are consistent with the nuclear density gauge 89% of the time for all types of soil tested. However, if the soils are more cohesive than the results are consistent with the nuclear density gauge 97% of the time. In addition these comparison tests are in general agreement with comparison compaction testing using the same testing techniques and methods of compacted backfill in utility trenches conducted earlier for the Public Works Department, Chesterfield County, Virginia

  18. The synthesis and investigation of impurities found in Clandestine Laboratories: Baeyer-Villiger Route Part I; Synthesis of P2P from benzaldehyde and methyl ethyl ketone.

    Science.gov (United States)

    Doughty, David; Painter, Ben; Pigou, Paul E; Johnston, Martin R

    2016-06-01

    The synthesis of impurities detected in clandestinely manufactured Amphetamine Type Stimulants (ATS) has emerged as more desirable than simple "fingerprint" profiling. We have been investigating the impurities formed when phenyl-2-propanone (P2P) 5, a key ATS precursor, is synthesised in three steps; an aldol condensation of benzaldehyde and methyl ethyl ketone (MEK); a Baeyer-Villiger reaction; and ester hydrolysis. We have identified and selectively synthesised several impurities that may be used as route specific markers for this series of synthetic steps. Specifically these impurities are 3-methyl-4-phenyl-3-buten-2-one 3, 2-methyl-1,5-diphenylpenta-1,4-diene-3-one 9, 2-(methylamino)-3-methyl-4-phenyl-3-butene 16, 2-(Methylamino)-3-methyl-4-phenylbutane 17, and 1-(methylamino)-2-methyl-1,5-diphenylpenta-4-ene-3-one 22. PMID:27081790

  19. Détention provisoire des jeunes femmes accusées d'avortement clandestin ou d'infanticide au Sénégal

    OpenAIRE

    Soumah, Mohamed Maniboliot; Pemba, Liliane Flore

    2012-01-01

    Introduction L'activité sexuelle chez les jeunes les expose à un accroissement du risque de contracter des grossesses non désirées. Le recours à l'avortement clandestin avec son corollaire de complications peut entrainer le décès de la jeune femme. Avortement et infanticide sont interdits et sanctionnés par la loi sénégalaise. Comment ces jeunes femmes vivent-elles leur détention? Existe-il des alternatives à la détention pour éviter leur désocialisation? Méthodes Cette étude rétrospective po...

  20. Plutonium isotopes and 137Cs in Dolon settlement near the Semipalatinsk Nuclear Test Site. About 50 years after the first nuclear weapon testing

    International Nuclear Information System (INIS)

    Recent controversies concerning the radiation doses for populations living in the village of Dolon due to the nuclear explosions carried out at the Semipalatinsk Nuclear Test Site (SNTS) have encouraged us to evaluate in more detail the levels and distributions of residual long-lived radionuclides 137Cs and Pu isotopes (238Pu, 239,240Pu) in soils within the village. Soil core samples up to a depth of about 30 cm and/or 100 cm were collected at 25 sites and subjected to analysis of 137Cs and Pu isotopes. The inventories of 137Cs and 239,240Pu were found to be in the wide range of 790-10,310 and 530-14,320 Bq/m2, respectively. Sequential leaching of Pu from the soil showed that more than ca. 80% of the 239,240Pu was not leached by hot digestion with conc. HNO3 + H2O2, indicating the presence of Pu associated with fused silicates. Further, the presence of hot-particles from the Pu contaminants by a-track radiography technique using CR-39 polycarbonate was confirmed in the soil, even at present, after about 50 years from the first nuclear weapon testing. (author)

  1. Nuclear energy consumption, oil consumption and economic growth in G-6 countries: Bootstrap panel causality test

    International Nuclear Information System (INIS)

    This study applies bootstrap panel Granger causality to test whether energy consumption promotes economic growth using data from G-6 countries over the period of 1971–2010. Both nuclear and oil consumption data are used in this study. Regarding the nuclear consumption-economic growth nexus, nuclear consumption causes economic growth in Japan, the UK, and the US; economic growth causes nuclear consumption in the US; nuclear consumption and economic growth show no causal relation in Canada, France and Germany. Regarding oil consumption-economic growth nexus, we find that there is one-way causality from economic growth to oil consumption only in the US, and that oil consumption does not Granger cause economic growth in G-6 countries except Germany and Japan. Our results have important policy implications for the G-6 countries within the context of economic development. - Highlights: ► Bootstrap panel Granger causality test whether energy consumption promotes economic growth. ► Data from G-6 countries for both nuclear and oil consumption data are used. ► Results have important policy implications within the context of economic development.

  2. Hot particles and the Cold War. Investigating fallout from nuclear testing

    International Nuclear Information System (INIS)

    Entering the next century, more than 2000 nuclear test explosions of various sizes and varieties will have been recorded. Nearly all of them were conducted during the Cold War period ending in the 1990s. Atmospheric nuclear tests dispersed radioactive residues into the environment. They are partitioned between the local ground (or water surface) and the tropospheric and stratospheric regions, depending on the type of test, location, and yield. The subsequent precipitation carrying the residues leads to both local and global fallout. Concentrations of certain radionuclides can result in formation of 'hot particles' - tiny bits of materials containing radioactive chemical elements. Local fallout includes large radioactive aerosols, particles which are generally deposited within about 100 kilometers of the test site. Local radioactive contamination at nuclear weapon test sites additionally is attributed to safety trials of nuclear devices that often dispersed fissile material. This material is released in various forms, including plutonium vapour, plutonium aerosols of various sizes, plutonium oxide particulates, plutonium-coated particles, and sizeable lumps of plutonium-contaminated structural material destroyed by the test explosion. Global fallout encompasses both tropospheric and stratospheric fallout. The first consists of aerosols that are not carried across the tropopause and that deposit With a mean residence time of up to 30 days. During this time, the residues become dispersed in the latitude band of injection, following trajectories governed by wind patterns. Stratospheric fallout arises from particles that later give rise to widespread global fallout, most of which is in the hemisphere where the nuclear test was conducted. It accounts for most of the residues of long-lived fission products

  3. FMCT after South Asia's tests. A view from a nuclear-weapon state

    International Nuclear Information System (INIS)

    Proposals to negotiate an international treaty to cutoff the production of plutonium and highly-enriched uranium for nuclear weapons have been on the international nuclear agenda for many decades. Hopes in the early 1990s that it would be possible finally to negotiate a FMCT, however, have not been borne out. Instead, a deadlock had ensued at the Geneva CD. It remains to be seen whether the recent nuclear tests by India and Pakistan will contribute to breaking that deadlock - or only to foreclosing any prospects for negotiating cutoff in the foreseeable future. The key lies in the attitudes of Delhi and Islamabad - influenced to the extent possible by the efforts of the international community to convince both countries' leaders to stop short of an escalating nuclear war in the region. Regardless, there are a variety of other initiatives aimed at heightening transparency and controls over the nuclear weapons materials in the five NPT nuclear weapon states that could be pursued as part of broader ongoing efforts to roll back the Cold War nuclear legacies

  4. Equipment and piping for nuclear power plants, test and research reactors, and nuclear installations

    International Nuclear Information System (INIS)

    The standard provides rules for testing the following welding operations: welding of ferritic pearlitic steels, welding of corrosion resistant austenitic steels, welding of components made of corrosion resistant austenitic steels and ferritic pearlitic steels, build-up welding of groove faces, and build-up welding of corrosion protecting layers

  5. Development of deterioration models and tests of structural materials for nuclear containment structures(III)

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Byung Hwan [Seoul National University, Seoul (Korea)

    2002-03-01

    The nuclear containment structures are very important infrastructures which require much cost for construction and maintenance. If these structures lose their functions and do not ensure their safety, great losses of human lives and properties will result. Therefore, the nuclear containment structures should secure appropriate safety and functions during these service lives. The nuclear concrete structures start to experience deterioration due to severe environmental condition, even though the concrete structures exhibit generally superior durability. It is, therefore, necessary to take appropriate actions at each stage of planning, design and construction to secure safety and functionability. Thorough examination of deterioration mechanism and comprehensive tests have been conducted to explore the durability characteristics of nuclear concrete structures. 88 refs., 70 figs., 12 tabs. (Author)

  6. Testing programs related to potential adverse flow effects in nuclear power plants

    International Nuclear Information System (INIS)

    Potential adverse flow effects on nuclear power plant Structures, Systems and Components (SSCs), can result from various causes. For example, reactor vessel and main steam system piping and components (including the steam dryer, safety relief and power-operated valves, and pipe supports) in BWR nuclear power plants can be damaged by pressure fluctuations and vibration resulting from acoustic resonances occurring in the main steam system or reactor vessel. The acoustic resonance phenomenon can also occur in pressurized water reactor (PWR) nuclear power plants with resulting damage to plant piping and components. Sampling probes in feedwater and condensate systems in nuclear power plants are also susceptible to adverse flow effects. The NRC staff reviews the evaluation performed by applicants for the construction and operation of nuclear power plants under 10 CFR Part 50 or Part 52 of the potential for adverse flow effects on plant SSCs. This proposed paper will discuss the various aspects of the programs established by applicants and licensees for monitoring plant data to verify that adverse flow effects are not occurring. These aspects of the test programs include the following: conducting walk-downs, and inspecting components during power ascension and operation at full licensed power conditions, dynamic response analysis of reactor internals under operational flow transients and steady-state conditions; preoperational flow-induced vibration testing of reactor internals; correlation of the test results with the analytical results. (authors)

  7. Proposition of law relative to the follow of sanitary and environmental consequences of nuclear tests

    International Nuclear Information System (INIS)

    The present proposition of law has for object to answer the expectation of all the persons who have participated as military personnel or civilians in nuclear tests made by France between February 13., 1960 and January 27., 1996, or lived near the nuclear test sites of Sahara (Reggane and In Eker) or in French Polynesia. The same pathologies are noticed among the veteran or the populations having lived near the nuclear tests sites of the other nuclear countries which made the same experiments. It is the case in United States, in Great Britain, in Australia, in New Zealand and in Fiji. In these different countries having a democratic system similar to ours, the governments took concrete measures to accede to the demands of their nationals. It thus turns out that a legislative initiative would represent a strong message of gratitude towards all those who had to undergo aftereffects on their health and that of their descendants of the only fact of their participation in the nuclear experiments of France. (N.C.)

  8. Proposition of law relative to the sanitary follow up of French nuclear tests

    International Nuclear Information System (INIS)

    The present proposition of law has for object to answer the expectation of all the persons who have participated as military personnel or civilians in nuclear tests made by France between February 13., 1960 and January 27., 1996, or lived near the nuclear test sites of Sahara (Reggane) or in French Polynesia. The same pathologies are noticed among the veteran or the populations having lived near the nuclear tests sites of the other nuclear countries which made the same experiments. It is the case in United States, in Great Britain, in Australia, in New Zealand and in Fidgi. In these different countries having a democratic system similar to ours, the governments took concrete measures to accede to the demands of their nationals. It thus turns out that a legislative initiative would represent a strong message of gratitude towards all those who had to undergo aftereffects on their health and that of their descendants of the only fact of their participation in the nuclear experiments of France. (N.C.)

  9. On the classification of structures, systems and components of nuclear research and test reactors

    International Nuclear Information System (INIS)

    The classification of structures, systems and components of nuclear reactors is a relevant issue related to their design because it is directly associated with their safety functions. There is an important statement regarding quality standards and records that says Structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. The definition of the codes, standards and technical requirements applied to the nuclear reactor design, fabrication, inspection and tests may be seen as the main result from this statement. There are well established guides to classify structures, systems and components for nuclear power reactors such as the Pressurized Water Reactors but one can not say the same for nuclear research and test reactors. The nuclear reactors safety functions are those required to the safe reactor operation, the safe reactor shutdown and continued safe conditions, the response to anticipated transients, the response to potential accidents and the control of radioactive material. So, it is proposed in this paper an approach to develop the classification of structures, systems and components of these reactors based on their intended safety functions in order to define the applicable set of codes, standards and technical requirements. (author)

  10. Beam Test for Evaluating Applicabillity of High - Strength Reinforcement in Structure of Nuclear Facility

    International Nuclear Information System (INIS)

    The high-strength rebar which has high yield strength can reduce the amount of rebar in concrete and widen its spacing so that it has better workability and higher economic benefits for the structure. However, the maximum yield strength of rebar is limited to 420MPa in the design criteria for structure of nuclear facility in Korea and USA. Korea Hydro and Nuclear Power is progressing research to revise the limitation in the yield strength of rebar, which is suggested in the criteria of KEPIC and ACI, in order to apply 550 MPa high-strength rebar for the construction of a nuclear facility. This study is to review the applicability of high strength rebar in structure of a nuclear facility through a model beam test. After reviewing the shear capacity and reinforcement yield to assess the applicability of high-strength reinforcement in the structure of a nuclear facility, we make the following conclusions. When using high shear reinforcement with wider spacing, it has a similar shear capacity to normal reinforcement with narrower spacing. This means better workability and economic benefits can be achieved by widening the rebar spacing without brittle fracture in the elements. For future plans, the results of this test and supplementary test will be submitted to ACI349 committee as backup data to revise the standard for yield strength of high-strength rebar

  11. La migration clandestine mexicaine comme un crime : commentaires sur quelques effets de la loi SB. 1070 de l’État de l’Arizona

    Directory of Open Access Journals (Sweden)

    Philippe Schaffhauser

    2011-11-01

    Full Text Available Cet article a pour objectif d’analyser les effets réels et possibles de l’entrée en vigueur en 2010 de la loi SB 1070, dite loi Arizona, laquelle se présente comme un dispositif juridique visant à lutter contre la migration clandestine dans cette partie de l’Union Américaine. Or cette loi a pour première conséquence pratique de criminaliser un type de situation migratoire et de stigmatiser ensuite la population mexicaine qui, selon les représentations sociales xénophobes, incarne para « excellence » (i.e. délit de facies, la figure du clandestin aux États-Unis. Être mexicain, dans ce pays, finit par être le commencement d’un délit ou du moins jette un doute sur la situation migratoire de l’ensemble des ressortissants de cette communauté nationale. L’article s’emploie à montrer l’arbitraire (l’État de l’Arizona comme tous les autres États de l’Union n’est pas compétent en matière de migration et la construction artificielle du délit imputé aux sans papiers. En effet, faire de la migration clandestine un crime pose le problème objectif de déterminer qui est la victime réelle d’un tel acte et, selon l’expression consacrée par John Stuart Mill, cette forme de migration apparaît au regard de la philosophie morale comme « crime sans victimes », puisque la seule victime de cette infraction à la loi c’est la société américaine toute entière, ses lois, ses normes, ses valeurs et ses institutions, soit une entité abstraite au regard de ce qui se joue au quotidien en matière migration clandestine et de contrôle policier.This article aims to examine the real effects and possible entry into force in 2010 of the so-called law SB 1070 Arizona law, which presents itself as a legal device to combat against illegal migration in this part of the American Union. However this Act is to first practical consequence criminalize a type of migratory situation and then condemn the Mexican population

  12. Laser-Ultrasonic Testing and its Applications to Nuclear Reactor Internals

    Science.gov (United States)

    Ochiai, M.; Miura, T.; Yamamoto, S.

    2008-02-01

    A new nondestructive testing technique for surface-breaking microcracks in nuclear reactor components based on laser-ultrasonics is developed. Surface acoustic wave generated by Q-switched Nd:YAG laser and detected by frequency-stabilized long pulse laser coupled with confocal Fabry-Perot interferometer is used to detect and size the cracks. A frequency-domain signal processing is developed to realize accurate sizing capability. The laser-ultrasonic testing allows the detection of surface-breaking microcrack having a depth of less than 0.1 mm, and the measurement of their depth with an accuracy of 0.2 mm when the depth exceeds 0.5 mm including stress corrosion cracking. The laser-ultrasonic testing system combined with laser peening system, which is another laser-based maintenance technology to improve surface stress, for inner surface of small diameter tube is developed. The generation laser in the laser-ultrasonic testing system can be identical to the laser source of the laser peening. As an example operation of the system, the system firstly works as the laser-ultrasonic testing mode and tests the inner surface of the tube. If no cracks are detected, the system then changes its work mode to the laser peening and improves surface stress to prevent crack initiation. The first nuclear industrial application of the laser-ultrasonic testing system combined with the laser peening was completed in Japanese nuclear power plant in December 2004.

  13. A sipping test simulator for identifying defective fuels in MTR type nuclear research reactor

    International Nuclear Information System (INIS)

    Highlights: • This simulator based on windows application of C# programming language. • This simulator could be useful for training of technicians in spent nuclear fuels storage facility. • This simulator is user friendly and easy to learn. - Abstract: Integrity of fuel assemblies is critical to continuous operation of any nuclear reactor. NDT methods and sipping test are practical techniques which are used for this purpose. Assessing the fuel integrity by NDT is a troublesome process which could incur personal overdose due to high radiation, requiring large space, and heavy equipment. Therefore to overcome problems associated with the NDT process, sipping test is widely used. The main purpose of this article is introducing sipping test simulator (STS) which is so important for training. Also, this article describes the procedure and methodology used to perform sipping test on the fuel assemblies either in reactor pool or spent fuel storage pool. A unique ability of this simulator is analyzing direct spectroscopy files from experimental data of a real operating reactor. The sipping test simulator is a full-feature training curriculum in spent nuclear fuels storage technology with a PC-based simulator. This simulator is written in C# programming language for a Windows based computer. The simulator will teach everything needed to know for identifying the fuel defects using sipping test process. As learning the basics of sipping test step wise, a freshman operator will soon be able to accomplish all steps in practice

  14. Thermal performance test through on-line turbine cycle performance monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Now under worldwide deregulation environment, the performance features of nuclear power plants (NPPs) become more important. A turbine cycle thermal performance test in an NPP is regarded as an important tool to improve plant economical efficiency. In this study, the feasibility and the technical issues for the turbine cycle thermal performance test through on-line monitoring are described. The performance test based on on-line monitoring is superior to the performance test by ASME Performance Test Code(PTC)s in the dynamic reflection of operating performance indexes. This advantage improves plant availability and saves resource needed in a performance test. However the critical technical issues such as 1) the security of an on-line data acquisition, 2) signal processing, and 3) plant simulation model development to implement useful on-line performance test concept because of the inherent characteristics of NPPs remain. Additionally the development strategy of a prototype on-line performance test system is proposed

  15. Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options

    International Nuclear Information System (INIS)

    The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents

  16. Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options.

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J. (Idaho National Laboratory, Idaho Falls, ID); Parma, Edward J., Jr.; Peters, Curtis D.; Vernon, Milton E.; Pickard, Paul S.

    2007-10-01

    The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents.

  17. The Comprehensive Nuclear-Test-Ban Treaty and Its Relevance for the Global Security

    Directory of Open Access Journals (Sweden)

    Dáša ADAŠKOVÁ

    2013-06-01

    Full Text Available The Comprehensive Nuclear-Test-Ban Treaty (CTBT is one of important international nuclear non-proliferation and disarmament measures. One of its pillars is the verification mechanism that has been built as an international system of nuclear testing detection to enable the control of observance of the obligations anchored in the CTBT. Despite the great relevance to the global non-proliferation and disarmament efforts, the CTBT is still not in force. The main aim of the article is to summarize the importance of the CTBT and its entry into force not only from the international relations perspective but also from the perspective of the technical implementation of the monitoring system.

  18. Operation fusileer onsite radiological safety report for announced nuclear tests, October 1983-September 1984

    International Nuclear Information System (INIS)

    Fusileer was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1983 through September 30, 1984. This report is limited to announced nuclear tests. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

  19. Development of fission gas sampling system for PWR spent nuclear fuel rods and test evaluation using dummy nuclear fuel rods

    International Nuclear Information System (INIS)

    Fission gas sampling system for measuring the fission gas quantity and internal pressure of PWR spent nuclear fuel rods was developed in KAERI. This system has the advantages of reducing the time required in equilibrium pressure by using as positive pressure in the chamber when the fission gas is expanded from the fuel rod to the puncturing and standard chamber, also improving the accuracy in measuring the fuel rod internal pressure. As a results of performance evaluation test using several dummy fuel rods in the inactive region, the accuracy of measuring system appeared to be good agreement within ±5% error range

  20. Proposition of law aiming to the recognition and indemnification of persons victims of nuclear tests or nuclear accident

    International Nuclear Information System (INIS)

    The present proposition of law has for object to establish the presumption of a relationship between on the one hand the nuclear weapons tests and on the other hand the pathologies developed by the civil or military personnel having worked on the concerned sites as well as the populations present in the contaminated areas. the present proposition aims to establish equality between the victims and to create the legal framework that will allow the state to proceed to the just compensations of damages imposed by actions then considered as national interest. (N.C.)

  1. The Iranian nuclear crisis a memoir

    CERN Document Server

    Mousavian, Seyed Hossein

    2012-01-01

    The first detailed Iranian account of the diplomatic struggle between Iran and the international community, The Iranian Nuclear Crisis: A Memoir opens in 2002, as news of Iran's clandestine uranium enrichment and plutonium production facilities emerge. Seyed Hossein Mousavian, previously the head of the Foreign Relations Committee of Iran'sSupreme National Security Council and spokesman for Tehran's nuclear negotiating team, brings the reader into Tehran's private deliberations as its leaders wrestle with internal and external adversaries.Mousavian provides readers with intim

  2. Guidelines for inservice testing at nuclear power plants. Draft report for comment

    International Nuclear Information System (INIS)

    In this report, the staff gives licensees guidelines for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The report includes U.S. Nuclear Regulatory Commission (NRC) guidance and recommendations on inservice testing issues. The staff discusses the regulations, the components to be included in an inservice testing program, and the preparation and content of cold shutdown and refueling outage justifications and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information for application at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

  3. In-situ testing of HEPA filters in the nuclear Karlsruhe filter system

    International Nuclear Information System (INIS)

    Nuclear plant operators and filter manufacturers are endeavouring to improve environmental protection by intensifying process control and/or improving filter quality. In-situ testing is an important element in these efforts since it represents a direct means of checking the success or otherwise of a particular development. The arrangements for in-situ testing should satisfy the following minimum requirements: the staff should not be exposed to risk during the test; the test method should be objective and reproducible as well as being as sensitive as possible; the test method should permit detection of individual leaks in the filter system so that they can be remedied as efficiently as possible; the test equipment should not necessitate modifications to the extract systems or plant construction; the test should be simple and capable of being carried out with a minimum of effort and equipment. GfK has developed the 'Nuclear-Karlsruhe' filter housing in accordance with these principles. This housing permits in-situ testing similar to the DIN 24184 visual oil-fog test or the DOP test. External visual checks on the general condition of the filter is also possible. A safe system of filter changing with a specially designed plastic bag attachment at an accessible height considerably increases the degree of protection of operating personnel

  4. The report of the Royal Commission into British nuclear tests in Australia

    International Nuclear Information System (INIS)

    The report examines in detail the British atomic tests conducted in Australia between 1952 and 1963. The background to the Australian involvement, nuclear weapons, radiation, radiological protection and radiation protection standards are discussed. For each trial the report looks at the choice of the testing site, the criteria for safe firing, fallout monitoring and the safety of aborigines and servicemen. The second volume covers the minor trials carried out at Emu and Maralinga and considers the security aspects of the tests. The state of the test sites and future management of the Range is discussed

  5. Vibration test report on crossover piping system in seismic isolation nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Uryu, Mitsuru; Shinohara, Takaharu; Terada, Shuji; Yamazaki, Toshihiko; Tomita, Tsuneo; Kondo, Toshinari

    1999-03-01

    In a seismic isolation nuclear facility, crossover piping system is subjected to large relative displacement and inertia forces during earthquakes. Hinged bellows expansion joints are utilized for accommodation to such the large displacement. This report describes tests for validation of developed simulation code with analytical models. Seismic experiments by a vibration test machine were conducted using actual size piping system models. A comparison between test results and analytical results showed a favorable agreement. The vibration test demonstrated that the structural integrity of this piping system would be maintained during earthquakes. (H. Itami)

  6. Residual radioactive contamination of the test site at Emu from nuclear weapons tests conducted in 1953

    International Nuclear Information System (INIS)

    The detailed distributions and soil concentrations of long-lived radionuclides remaining from nuclear weapons trials conducted at Emu in October 1953, are presented. Significant radiation levels due to long-lived neutron activation products in soil, 60Co and 152Eu, occur only in the immediate vicinity of the ground zeros of TOTEM 1 and TOTEM 2. It is shown that the levels of contamination due to fallout products in the soil are well below those which would constitute a health hazard to occupants of the area

  7. The role of equilibrium leach testing in understanding the behaviour of nuclear wastes under disposal conditions

    International Nuclear Information System (INIS)

    Results from the equilibrium leach testing of a range of intermediate level nuclear wastes have been modelled using sorption and solubility data obtained in experiments with individual radionuclides. The wastes involved were AGR hulls, Magnox cladding wastes, combustible plutonium-contaminated materials and ferric/aluminium hydroxide flocs. The test has an important role in validating near-field models, and helps to build confidence in disposal assessments. (author)

  8. Evaluation of the contribution made by different tests in nuclear medicine to occupational dose

    International Nuclear Information System (INIS)

    The Department of Nuclear Medicine from the Cancer Hospital at Camaguey y is described based on the evaluation of the contribution to the collective dose of different tests carried out at the department. Studies were made starting from statistics from tests in 1995 -1996 and the dose measurements made during the execution of different procedures. Outcomes are compared with those from the individual dosimetric control using the film dosimetry service from the CPHR during 1995 -1996

  9. Fallout in East Tennessee following Chinese nuclear tests of 1976 to 1978

    International Nuclear Information System (INIS)

    The fallout levels in East Tennessee following the Chinese nuclear tests of 1976 to 1978 are given. The environmental surveillance activities at Oak Ridge National Laboratory are outlined, as well as their integration into the nationwide monitoring network. A method for rapid determination of 131I in milk is described; these levels in milk are highlighted, along with airfilter and rainwater data. Maximum radiological dose commitments, as a result of the recent tests, are presented

  10. The role equilibrium leach testing in understanding the behaviour of nuclear wastes under disposal conditions

    International Nuclear Information System (INIS)

    Results from the equilibrium leach testing of a range of intermediate level nuclear wastes have been modelled successfully using sorption and solubility data obtained in experiments with individual radionuclides. The wastes involved included fuel cladding (after removal of irradiated fuel for reprocessing), combustible plutonium-contaminated materials and ferric/aluminium hydroxide flocs. The test has an important role in validating nearfield models, and helps to build confidence in disposal assessments. (orig.)

  11. Tests for determining impact resistance and strength of glass used for nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Bunnell, L.R.

    1979-05-01

    Tests are described for determining the impact resistance (Section A) and static tensile strength (Section B) of glasses containing simulated or actual nuclear wastes. This report describes the development and use of these tests to rank different glasses, to assess effects of devitrification, and to examine the effect of impact energy on resulting surface area. For clarity this report is divided into two sections, Impact Resistance and Tensile Strength.

  12. The software testing of PPS for shin Ulchin nuclear power plant units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dong Pa; Park, Cheol Lak; Cho, Chang Hui; Sohn, Se Do; Baek, Seung Min [KEPCO Engineering and Construction Company, Daejeon (Korea, Republic of)

    2012-10-15

    The testing of software (S/W) is the process of analyzing a software item to detect the differences between existing and required conditions to evaluate the features of the software items. This paper introduces the S/W testing of Plant Protection System (PPS), as a safety system which actuate Reactor Trip (RT) and Engineered Safety Features (ESF) for Shin Ulchin Nuclear Power Plant Units 1 and 2 (SUN 1 and 2)

  13. Tests for determining impact resistance and strength of glass used for nuclear waste disposal

    International Nuclear Information System (INIS)

    Tests are described for determining the impact resistance (Section A) and static tensile strength (Section B) of glasses containing simulated or actual nuclear wastes. This report describes the development and use of these tests to rank different glasses, to assess effects of devitrification, and to examine the effect of impact energy on resulting surface area. For clarity this report is divided into two sections, Impact Resistance and Tensile Strength

  14. Application of analytical techniques of nuclear geology in the test for shale gas exploration and exploitation

    International Nuclear Information System (INIS)

    In the past 50 years, the nuclear geoanalysis methods are developed for analysis of elements, nuclides, isotopes, microzone and organic compounds. Those methods may also be applied to the test for shale gas exploration. The main testing parameters, analytical techniques and the instruments for shale gas exploration are reviewed. The stated parameters include TOC, gas storage contents, gas composition, stable isotopes (C, H, He), thermal maturity (Ro), Langmuir isotherm, porosity, permeability, mineral composition, and 3D microstructure imaging. (authors)

  15. Economic comparison of an improved nuclear filter system considering space, operation, testing, and maintenance costs

    International Nuclear Information System (INIS)

    The development of an all-welded charcoal adsorber design for increased system iodine removal efficiency has provided certain other unique advantages of particular interest to nuclear power plant personnel involved in health/safety, operation, maintenance, testing and space allocation for nuclear filter systems. The design features providing these unique advantages have been refined and tested and are available and installed on operating reactors as the HECA filter system. Health/safety aspects of the system are improved through the use of a unique pneumatic conveying system which eliminates the need for entrance of maintenance personnel into the filter housing during removal and replacement of spent charcoal and; thereby, minimizes radiation exposure of occupational personnel. Operational and maintenance costs, after capital investment, for nuclear filter systems being of particular interest to utility operations management are compared with conventional iodine absorber systems. The material cost savings in charcoal replacement with the system can exceed capital investment costs for given operating conditions. Testing and retest for by-pass leakage location and correction experiences are described and comparisons drawn between the HECA system and conventional designs. Space allocation improvements for actual nuclear filter system installations are described using the HECA system in conjunction with 1500 CFM ''superflow'' absolute filter modules. Features of the separatorless absolute superflow filter that complement the like design features of the all-welded HECA charcoal adsorber are described and operational and test data are presented. (U.S.)

  16. British Nuclear Test Veterans' Association. Radiation exposure and subsequent health history of veterans and their children

    International Nuclear Information System (INIS)

    The present study of veterans' health carried out in association with Tyne Tees Television presents new and disturbing evidence of significant health effects in both veterans and their children, based on the health records of 1,454 members of the British Nuclear Test Veterans' Association, of whom 1,147 were fathers. (orig./MG)

  17. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982

    Energy Technology Data Exchange (ETDEWEB)

    Black, S. C.; Grossman, R. F.; Mullen, A. A.; Potter, G. D.; Smith, D. D. [comps.

    1983-07-01

    A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982.

  18. Current developments in mechanized non-destructive testing in nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

  19. The nondestructive testing concept applied in the construction of nuclear power plant

    International Nuclear Information System (INIS)

    Nuclear power plant components consisting of sheet metal, pipes, forgings and castings, and their various welded joints, the lecture illustrates the NDT concept referring to examples of testing work with manufactured parts or welded joints, taking into account safety categories and quality classes. (orig.)

  20. Rehabilitation of the former nuclear test sites in Australia. Report by the Technical Assessment Group

    International Nuclear Information System (INIS)

    The note outlines the findings of the Australian Governments Technical Assessment Group Studies which provide information on the Rehabilitation of the Former Nuclear Test Sites in Australia, with particular attention to the lifestyle and dietary habits of an Aboriginal community who may wish to live permanently on the Maralinga Range. (UK)

  1. Potential Benefits of the Comprehensive Nuclear-Test-Ban Treaty Organization to Ghana

    Directory of Open Access Journals (Sweden)

    P. Amponsah

    2014-03-01

    Full Text Available The National Data Centers established around the globe with the support of the Comprehensive Nuclear Test Ban Treaty Organization are used to monitor and manage its data, to control and ultimately eliminate nuclear weapon test explosions. The National Data Center in Ghana was established in February, 2010 at the Ghana Atomic Energy Commission. The Center is mandated to collate seismic, radionuclide, infrasound and hydroacoustic data for monitoring nuclear test explosions for global peace. The data are obtained from our neighboring country Cote d’Ivoire and the International Data Center in Austria. The objectives of the Data Center include the following: receive and use data from the International Monitoring System (IMS stations and products derived from the IMS from the International Data Center for verification and compliance of the Comprehensive Nuclear Test Ban Treaty and for earthquake hazard studies. From 2010 to date local seismic events from the Center are catalogued for earthquake hazard studies in the country. The data are also made available to our stakeholders for earthquake disaster risk reduction. The benefits of the National Data Center to Ghana are numerous. Apart from the data for seismic hazard studies, it can also provide data for research in fisheries, for the study of the crustal structure among others. DOI: http://dx.doi.org/10.5755/j01.erem.67.1.5402

  2. Potential Benefits of the Comprehensive Nuclear-Test-Ban Treaty Organization to Ghana

    Directory of Open Access Journals (Sweden)

    Paulina Amponsah

    2014-04-01

    Full Text Available The National Data Centers established around the globe with the support of the Comprehensive Nuclear Test Ban Treaty Organization are used to monitor and manage its data, to control and ultimately eliminate nuclear weapon test explosions. The National Data Center in Ghana was established in February, 2010 at the Ghana Atomic Energy Commission. The Center is mandated to collate seismic, radionuclide, infrasound and hydroacoustic data for monitoring nuclear test explosions for global peace. The data are obtained from our neighboring country Cote d’Ivoire and the International Data Center in Austria. The objectives of the Data Center include the following: receive and use data from the International Monitoring System (IMS stations and products derived from the IMS from the International Data Center for verification and compliance of the Comprehensive Nuclear Test Ban Treaty and for earthquake hazard studies. From 2010 to date local seismic events from the Center are catalogued for earthquake hazard studies in the country. The data are also made available to our stakeholders for earthquake disaster risk reduction. The benefits of the National Data Center to Ghana are numerous. Apart from the data for seismic hazard studies, it can also provide data for research in fisheries, for the study of the crustal structure among others.

  3. Characteristics of broken soils at the former Azgir nuclear test site

    International Nuclear Information System (INIS)

    There were determined phase and element compositions of day surface soil ground of technological locations of the former Azgir nuclear test site. The data on radionuclide contamination of soil ground at a number of locations and the distribution of cesium-137 on granulometric soil fractions has been presented. (author)

  4. Review of recent benchmark experiments on integral test for high energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi; Tanaka, Susumu; Konno, Chikara; Fukahori, Tokio; Hayashi, Katsumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    A survey work of recent benchmark experiments on an integral test for high energy nuclear data evaluation was carried out as one of the work of the Task Force on JENDL High Energy File Integral Evaluation (JHEFIE). In this paper the results are compiled and the status of recent benchmark experiments is described. (author)

  5. A description of the helium corrosion test facility at Springfields Nuclear Power Development Laboratories

    International Nuclear Information System (INIS)

    The construction and mode of operation of the helium test loops at the Springfields Nuclear Power Development Laboratories are described and the experimental procedure is detailed. The facility is for the controlled corrosion of reactor materials in helium-based or other gaseous environments. The corroded specimens may be used for the assessment of any resulting chemical, physical and mechanical, parameter changes. (author)

  6. THE MAIN DIRECTIONS OF PROSPECTIVE COHORT STUDY OF POPULATION LIVING AROUND THE SEMIPALATINSK NUCLEAR TEST SITE

    OpenAIRE

    ZHUNUSSOVA T.; Grosche, B; Apsalikov, K.; BELIKHINA T.; Pivina, L.; Muldagaliev, T.

    2014-01-01

    In the paper we have presented the possibilities of prospective cohort study of health status in the radiation exposed population living around the Semipalatinsk nuclear test site. It was substantiated the necessity of international cooperation of scientists from Kazakhstan, Europe, Japan and the United States for long-term study of radiation effects for the people and the environment.

  7. JAEA's recent activities related to Comprehensive Nuclear-Test-Ban Treaty (CTBT)

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT), which bans any nuclear test at any place on the earth and provides the establishment of a system to monitor compliance by member states, was adopted at the United Nations in 1996. At present, more than 80% facilities (276 places) of the International Monitoring System (IMS) prescribed in the treaty have already been completed and have been substantially functioning as a global nuclear test monitoring. Of facilities installed in Japan, the Japan Atomic Energy Agency (JAEA) has established two radionuclide (RN) stations (Onna-son, Okinawa and Takasaki, Gunma) which monitor radionuclides and one radionuclide laboratory (Tokai, Ibaraki) for detail analyses of samples sent from RN stations all over the world, and JAEA is operating them as certified facilities meeting technical requirements for the Treaty monitoring. The National Data Center (NDC) installed in JAEA's site (Tokai, Ibaraki) receives the data from station network and analyzes them routinely. This paper describes current status of the verification regime and JAEA's recent activities related to the CTBT such as analysis and evaluation of the DPRK's 3rd nuclear test event. (author)

  8. Monitoring of temperature anomalies in the former Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    The space Research Institute of the Ministry of Science, Academy of Sciences of Kazakhstan, monitors the territory of Kazakhstan using the NOAA satellite data. This year, significant anomalies in the distribution of snow cover and underlying surface temperature have been detected in the region of the former Semipalatinsk nuclear test site (SNTS). (authors)

  9. Follow-up of the results of the nuclear power plant stress tests and action plan

    International Nuclear Information System (INIS)

    The results of the stress tests carried out by the European nuclear power plants in the wake of the Fukushima Daiichi accident, subsequently subjected to peer reviews, have made it possible to identify the measures to be applied to improve safety. Action plans have been put in place to implement these measures within appropriate time frames. (Author)

  10. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982

    International Nuclear Information System (INIS)

    A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982

  11. Tests of nuclear weapons and the beginning of radioactivity monitoring using the example of Switzerland

    International Nuclear Information System (INIS)

    A historical survey is given on the development and the tests of nuclear weapons including the consequences for humans and the environment, as well as on the generation of measuring networks for radioactivity in the environment in the same time. Some results of the measurements are shown exemplarily for Switzerland.

  12. The startup tests for TRIGA Mark II at the Institute for Nuclear Energy

    International Nuclear Information System (INIS)

    This paper briefly describes the start-up tests for TRIGA Mark-II at the Institute for Nuclear Energy and some of the problems during the construction. This Report consists of three parts: 1. Shield Construction and Installation of ITU-TRR Components. 2. Start-up Experiments. 3. Experience Gained in Operation and Maintenance

  13. Design of Testing Set-up for Nuclear Fuel Rod by Neutron Radiography at CARR

    Institute of Scientific and Technical Information of China (English)

    WEI; Guo-hai; HAN; Song-bai; WANG; Hong-li; HAO; Li-jie; WU; Mei-mei; HE; Lin-feng; WANG; Yu; LIU; Yun-tao; SUN; Kai; CHEN; Dong-feng

    2012-01-01

    <正>An experimental set-up dedicated to non-destructively test a 15 cm long pressurized water reactor (PWR) nuclear fuel rod by neutron radiography (NR) is designed and fabricated. It consists of three parts: Transport container, imaging block and steel support. The design of the transport container was optimized with Monte-Carlo simulation by the MCNP code.

  14. Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

    International Nuclear Information System (INIS)

    Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National Laboratories, the 1980's

  15. Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

    Energy Technology Data Exchange (ETDEWEB)

    Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge Northridge, CA 91330 (United States)

    2012-07-01

    Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National

  16. Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment

    Energy Technology Data Exchange (ETDEWEB)

    David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

    2012-07-01

    In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

  17. Full-scale impact test data for tornado-missile design of nuclear plants

    International Nuclear Information System (INIS)

    It is standard practice to consider the effects of low-probability impacts of tornado-borne debris (''tornado missiles'' such as utility poles and steel pipes) in the structural design of nuclear power plants in the United States. To provide data that can be used directly in the design procedure, a series of full-scale tornado-missile impact tests was performed. This paper is a brief summary of the results and conclusions from these tests. The tests consisted of reinforced concrete panels impacted by poles, pipes, and rods propelled by a rocket sled. The panels were constructed to current minimum standards and had thicknesses typical of auxiliary buildings of nuclear power plants. A specific objective was the determination of the impact velocities below which the panels do not experience backface scabbing. Another objective was to assess the adequacy of (1) conventional design formulae for penetration and scabbing and (2) conventional design methods for overall structural response. Test missiles and velocities represented those in current design standards. Missiles included utility poles, steel pipes, and steel bars. It is important to interpret the data in this paper in recognition that the test conditions represent conservative assumptions regarding maximum wind speeds, injection of the missile into the wind stream, aerodynamic trajectory, and orientation of missile at impact. Even with the severe assumptions made, the full-scale tests described demonstrate the ability of prototypical nuclear plant walls and roofs to provide adequate protection against postulated tornado-missile impact

  18. Nuclear weapons test detection: Ensuring a verifiable treaty. Comprehensive Test Ban Treaty research and development program 1995 progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The US Department of Energy (DOE) has an active program to provide technologies for monitoring and verifying a Comprehensive Test Ban Treaty (CTBT). DOE technologies will significantly increase the nation`s capability to identify potential nuclear explosions with high confidence and with minimal false alarms. This report presents the highlights of the first year of this program. The primary objectives of the CTBT monitoring system are to deter nuclear explosions in all environments (underground, underwater, or in the atmosphere) and, if such an explosion does occur, to detect, locate, and identify its source. The system is designed to provide credible evidence to national authorities to aid in resolving ambiguities and to serve as the basis for appropriate action. To collect this evidence, one must develop technologies that can detect and identify the signals from a nuclear test against a background of hundreds of thousands of benign events. The monitoring system must have high sensitivity to detect the events of interest and, to minimize false alarms, it must identify those events with a high level of confidence.

  19. Peaceful Nuclear Explosion Datasets for Seismic Research and Nuclear Test Monitoring

    Science.gov (United States)

    Smithson, S. B.; Morozov, I. B.; Morozova, E. A.; Richards, P. G.; Solodilov, L. N.

    2001-12-01

    Within the next four years, IRIS databases will receive from the University of Wyoming and GEON recordings from nine ultra-long range Deep Seismic Sounding (DSS) projects conducted between 1970-1989 in the former Soviet Union: QUARTZ, CRATON, KIMBERLITE, METEORITE, RIFT, RUBY, BATHOLIT, BAZALT, and AGATE. Jointly sponsored by the Department of Defense and National Science Foundation, this effort will bring the unique recordings of 22 Peaceful Nuclear Explosions (PNEs) and hundreds of crustal-scale chemical shots to the broad seismological and monitoring research communities. A grid of reversed PNE profiles (plus fan recording for RUBY) covers the East European Platform, the Ural Mountains, the West Siberian Platform, the Siberian craton, and the Baikal Rift. Dense, 3-component, short-period recordings along these profiles provide a valuable source of seismic information for seismic calibration of these vast aseismic regions. DSS recordings offer unique opportunities to study propagation effects of body waves and regional seismic phases, to examine their correlation with geologic and tectonic features, to develop unusually well constrained models of the structure of the crust and upper mantle to 600-700 km depth, and to explore the variability of explosion discriminants such as spectral ratios of P- and S-waves. Though the data principally concern properties of the crust and upper mantle, some of the profiles also show strong reflections from the core-mantle boundary. We summarize the recent findings from the analysis of PNE datasets in Northern Eurasia. These results include (1) unusually detailed velocity and attenuation structure of the crust and uppermost mantle, (2) characterization of crustal attenuation through coda measurements, (3) constraints on seismic scattering from within the crust and uppermost mantle, (4) detailed imaging of the crustal basement using receiver functions, (5) continuous observations of the regional phases from the PNEs within 0

  20. Development of Phenomenological Models of Underground Nuclear Tests on Pahute Mesa, Nevada Test Site - BENHAM and TYBO

    Energy Technology Data Exchange (ETDEWEB)

    Pawloski, G.A.

    1999-09-21

    Although it is well accepted that underground nuclear explosions modify the in situ geologic media around the explosion point, the details of these changes are neither well understood nor well documented. As part of the engineering and containment process before a nuclear test, the physical environment is characterized to some extent to predict how the explosion will interact with the in situ media. However, a more detailed characterization of the physical environment surrounding an expended site is needed to successfully model radionuclide transport in the groundwater away from the detonation point. It is important to understand how the media have been altered and where the radionuclides are deposited. Once understood, this information on modified geologic media can be incorporated into a phenomenological model that is suitable for input to computer simulations of groundwater flow and radionuclide transport. The primary goals of this study are to (1) identify the modification of the media at a pertinent scale, and (2) provide this information to researchers modeling radionuclide transport in groundwater for the US Department of Energy (DOE) Nevada Operations Office Underground Test Area (UGTA) Project. Results from this study are most applicable at near-field scale (a model domain of about 500 m) and intermediate-field scale (a model domain of about 5 km) for which detailed information can be maximized as it is incorporated in the modeling grids. UGTA collected data on radionuclides in groundwater during recent drilling at the ER-20-5 site, which is near BENHAM and TYBO on Pahute Mesa at the Nevada Test Site (NTS). Computer simulations are being performed to better understand radionuclide transport. The objectives of this modeling effort include: evaluating site-specific information from the BENHAM and TYBO tests on Pahute Mesa; augmenting the above data set with generalized containment data; and developing a phenomenological model suitable for input to

  1. Development of an automated testing system for verification and validation of nuclear data

    International Nuclear Information System (INIS)

    Verification and validation of nuclear data is critical to the accuracy of both stochastic and deterministic particle transport codes. In order to effectively test a set of nuclear data, the data must be applied to a wide variety of transport problems. Performing this task in a timely, efficient manner is tedious. The nuclear data team at Los Alamos National Laboratory (LANL) in collaboration with the University of Florida is developing a methodology to automate the process of nuclear data verification and validation. The International Criticality Safety Benchmark Experiment Project (ICSBEP) provides a set of criticality problems that may be used to evaluate nuclear data. This process tests a number of data libraries using cases from the ICSBEP benchmark set to demonstrate how automation of these tasks may reduce errors and increase efficiency. The process is driven by an integrated set of Python scripts. Material and geometry data may be read from an existing code input file to generate a standardized template or the template may be generated directly by the user The user specifies the desired precision and other vital problem parameters. The Python scripts generate input decks for multiple transport codes from these templates, run and monitor individual jobs, and parse the relevant output. This output can then be used to generate reports directly or can be stored into a database for later analysis. This methodology eases the burden on the user by reducing the amount of time and effort required for obtaining and compiling calculation results. (authors)

  2. Radiation doses to local populations near nuclear weapons test sites worldwide.

    Science.gov (United States)

    Simon, Steven L; Bouville, André

    2002-05-01

    Nuclear weapons testing was conducted in the atmosphere at numerous sites worldwide between 1946 and 1980, which resulted in exposures to local populations as a consequence of fallout of radioactive debris. The nuclear tests were conducted by five nations (United States, Soviet Union, United Kingdom, France, and China) primarily at 16 sites. The 16 testing sites, located in nine different countries on five continents (plus Oceania) contributed nearly all of the radioactive materials released to the environment by atmospheric testing; only small amounts were released at a fewother minor testing sites. The 16 sites discussed here are Nevada Test Site, USA (North American continent), Bikini and Enewetak, Marshall Islands (Oceania); Johnston Island, USA (Oceania), Christmas and Malden Island, Kiribati (Oceania); Emu Field, Maralinga, and Monte Bello Islands, Australia (Australian continent); Mururoa and Fangataufa, French Polynesia (Oceania), Reggane, Algeria (Africa), Novaya Zemlya and Kapustin Yar, Russia (Europe), Semipalatinsk, Kazakhstan (Asia), and Lop Nor, China (Asia). There were large differences in the numbers of tests conducted at each location and in the total explosive yields. Those factors, as well as differences in population density, lifestyle, environment, and climate at each site, led to large differences in the doses received by local populations. In general, the tests conducted earliest led to the highest individual and population exposures, although the amount of information available for a few of these sites is insufficient to provide any detailed evaluation of radiation exposures. The most comprehensive information for any site is for the Nevada Test Site. The disparities in available information add difficulty to determining the radiation exposures of local populations at each site. It is the goal of this paper to summarize the available information on external and internal doses received by the public living in the regions near each of the

  3. Radiation doses to local populations near nuclear weapons test sites worldwide

    International Nuclear Information System (INIS)

    Nuclear weapons testing was conducted in the atmosphere at numerous sites worldwide between 1946 and 1980, which resulted in exposures to local populations as a consequence of fallout of radioactive debris. The nuclear tests were conducted by five nations (United States, Soviet Union, United Kingdom, France, and China) primarily at 16 sites. The 16 testing sites, located in nine different countries on five continents (plus Oceania) contributed nearly all of the radioactive materials released to the environment by atmospheric testing; only small amounts were released at a few other minor testing sites. The 16 sites discussed here are Nevada Test Site, USA (North American continent), Bikini and Enewetak, Marshall Islands (Oceania); Johnston Island, USA (Oceania), Christmas and Malden Island, Kiribati (Oceania); Emu Field, Maralinga, and Monte Bello Islands, Australia (Australian continent); Mururoa and Fangataufa, French Polynesia (Oceania), Reggane, Algeria (Africa), Novaya Zemlya and Kapustin Yar, Russia (Europe), Semipalatinsk, Kazakhstan (Asia), and Lop Nor, China (Asia). There were large differences in the numbers of tests conducted at each location and in the total explosive yields. Those factors, as well as differences in population density, lifestyle, environment, and climate at each site, led to large differences in the doses received by local populations. In general, the tests conducted earliest led to the highest individual and population exposures, although the amount of information available for a few of these sites is insufficient to provide any detailed evaluation of radiation exposures. The most comprehensive information for any site is for the Nevada Test Site. The disparities in available information add difficulty to determining the radiation exposures of local populations at each site. It is the goal of this paper to summarize the available information on external and internal doses received by the public living in the regions near each of the

  4. Assessment of hydrologic transport of radionuclides from the Gnome underground nuclear test site, New Mexico

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, 90Sr, and 137Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test

  5. Bounds test approach to cointegration and causality between nuclear energy consumption and economic growth in India

    International Nuclear Information System (INIS)

    This paper attempts to examine the dynamic relationship between economic growth, nuclear energy consumption, labor and capital for India for the period 1969-2006. Applying the bounds test approach to cointegration developed by we find that there was a short- and a long-run relationship between nuclear energy consumption and economic growth. Using four long-run estimators we also found that nuclear energy consumption has a positive and a statistically significant impact on India's economic growth. Further, applying the approach to Granger causality and the variance decomposition approach developed by , we found a positive and a significant uni-directional causality running from nuclear energy consumption to economic growth without feedback. This implies that economic growth in India is dependent on nuclear energy consumption where a decrease in nuclear energy consumption may lead to a decrease in real income. For a fast growing energy-dependent economy this may have far-reaching implications for economic growth. India's economic growth can be frustrated if energy conservation measures are undertaken without due regard to the negative impact they have on economic growth.

  6. Development of a test suite for nuclear data verification and validation

    International Nuclear Information System (INIS)

    Verification and validation of nuclear data is critical to the accuracy of both stochastic and deterministic particle transport codes. In order to effectively test a set of nuclear data, the data must be applied to a wide variety of transport problems. Performing this task in a timely, efficient manner is tedious. The nuclear data team at Los Alamos National Laboratory in collaboration with the University of Florida has developed a methodology to automate the process of nuclear data verification and validation (V and V). This automated V and V process can efficiently test a number of data libraries using well defined benchmark experiments, such as those in the International Criticality Safety Benchmark Experiment Project (ICSBEP). The process is implemented through an integrated set of Python scripts. Material and geometry data are read from an existing medium or given directly by the user to generate a benchmark experiment template file. The user specifies the choice of benchmark templates, codes, and libraries to form a V and V project. The Python scripts generate input decks for multiple transport codes from the templates, run and monitor individual jobs, and parse the relevant output automatically. The output can then be used to generate reports directly or can be stored into a database for later analysis. This methodology eases the burden on the user by reducing the amount of time and effort required for obtaining and compiling calculation results. The resource savings by using this automated methodology could potentially be an enabling technology for more sophisticated data studies, such as nuclear data uncertainty quantification. Once deployed, this tool will allow the nuclear data community to more thoroughly test data libraries leading to higher fidelity data in the future. (authors)

  7. Reflections on nuclear challenges today. 6 December 2005, London, UK, International Institute for Strategic Studies, Allistair Buchan Lecture

    International Nuclear Information System (INIS)

    Emerging nuclear challenges are proliferation of nuclear weapons and sensitive nuclear technologies, emergence of nuclear clandestine procurement networks in nuclear materials and equipment and the sluggishment in nuclear disarmament. Practical steps to address them are 1) better control of access to nuclear fuel cycle technology; 2) supporting effective nuclear verification; 3) strengthening the credibility of enforcement mechanisms; 4) protecting nuclear material and 5) developing an alternative approach to collective security. For better control of access to nuclear fuel cycle technology a group of international experts proposes to a) provide assurance of supply of reactor technology and nuclear fuel; b) accept a time-limited moratorium (of perhaps 5-10 years) on new uranium enrichment and plutonium separation facilities - at the very least for countries that do not currently have such technologies; c) establish a framework for multilateral management and control of the 'back end' of the fuel cycle (i.e. spent fuel reprocessing and waste disposal); and d) create a similar framework for multilateral management and control of the 'front end' of the fuel cycle (i.e. enrichment and fuel production). The effectiveness of nuclear verification depends on the extend of access to information and locations in a given country and inspections can only verify what countries declare. The expanded access provided by the Additional Protocol to safeguards agreements enables the Agency to verify possible undeclared activities however both safeguards agreements are focused on nuclear material and therefore the Agency's authority to investigate possible parallel weaponization activity is limited. In addition only 70 countries have the additional protocol on force. Additional transparency measures' may be required as well as additional funding to support R and D on new technologies for detecting clandestine nuclear facilities and activity. An important step to address the nuclear

  8. Application of IAEA's International Nuclear Event Scale to events at testing/research reactors in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Nozawa, Masao [Research Organization for Information Science and Technology, Tokai, Ibaraki (Japan); Watanabe, Norio

    1999-08-01

    The International Nuclear Event Scale (INES) is a means for providing prompt, clear and consistent information related to nuclear events and facilitating communication between the nuclear community, the media and the public on such events. This paper describes the INES rating process for events at testing/research reactors and nuclear fuel processing facilities and experience on the application of the INES scale in Japan. (author)

  9. OSIRIS—Gamma-ray spectroscopy software for on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty

    International Nuclear Information System (INIS)

    We have designed and tested software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—OSIRIS—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,131I. A set of over 100 fission-product spectra was employed for OSIRIS testing. These spectra were measured where possible, or generated by modeling. The test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, OSIRIS correctly identifies CTBT-relevant fission product isotopes at the 95% level or better

  10. OSIRIS-Gamma-ray spectroscopy software for on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty

    Science.gov (United States)

    Caffrey, A. J.; Bowyer, T. W.; Egger, A. E.; Hall, J. C.; Kelly, S. M.; Krebs, K. M.; Kreek, S. A.; Jordan, D. V.; Milbrath, B. D.; Padgett, S. W.; Wharton, C. J.; Wimer, N. G.

    2015-06-01

    We have designed and tested software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-OSIRIS-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,131I. A set of over 100 fission-product spectra was employed for OSIRIS testing. These spectra were measured where possible, or generated by modeling. The test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, OSIRIS correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.

  11. OSIRIS—Gamma-ray spectroscopy software for on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty

    Energy Technology Data Exchange (ETDEWEB)

    Caffrey, A.J., E-mail: Gus.Caffrey@inl.gov [Idaho National Laboratory, Idaho Falls, ID (United States); Bowyer, T.W. [Pacific Northwest National Laboratory, Richland, WA (United States); Egger, A.E. [Idaho National Laboratory, Idaho Falls, ID (United States); Hall, J.C. [Pacific Northwest National Laboratory, Richland, WA (United States); Kelly, S.M.; Krebs, K.M. [Idaho National Laboratory, Idaho Falls, ID (United States); Kreek, S.A. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Jordan, D.V.; Milbrath, B.D. [Pacific Northwest National Laboratory, Richland, WA (United States); Padgett, S.W. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Wharton, C.J. [Idaho National Laboratory, Idaho Falls, ID (United States); Wimer, N.G. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

    2015-06-01

    We have designed and tested software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—OSIRIS—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,{sup 131}I. A set of over 100 fission-product spectra was employed for OSIRIS testing. These spectra were measured where possible, or generated by modeling. The test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, OSIRIS correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.

  12. Radionuclide Observables for the Platte Underground Nuclear Test on 14 April 1962

    Energy Technology Data Exchange (ETDEWEB)

    Burnett, Jonathan L.; Milbrath, Brian D.

    2016-08-02

    Past nuclear weapons tests provide invaluable information for understanding the radionuclide observables and data quality objectives expected during an On-site Inspection (OSI) for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). These radioactive signatures are complex and subject to spatial and temporal variability. The Platte Underground Nuclear Test on 14 April 1962 provides extensive environmental monitoring data that can be modelled and used to assess an OSI. The 1.6 kT test is especially useful as it released the highest amounts of recorded activity during Operation Nougat at the Nevada Test Site – now known as the Nevada National Security Site (NNSS). It has been estimated that 0.36% of the activity was released, and dispersed in a northerly direction. The deposition ranged from 1 x 10-11 to 1 x 10-9 of the atmospheric release (per m2), and has been used to evaluate a hypothetical OSI at 1 week to 2 years post-detonation. Radioactive decay reduces the activity of the 17 OSI relevant radionuclides by 99.7%, such that detection throughout the inspection is only achievable close to the explosion where deposition was highest.

  13. The US National Resources Defense Council/Soviet Academy of Sciences Nuclear Test Ban Verification Project

    International Nuclear Information System (INIS)

    The first week in September 1987 was an extraordinary one for arms control verification. As part of the co-operative Test Ban Verification Project of the Natural Resources Defense Council (NRDC) and the Soviet Academy of Sciences, fourteen American scientists from the Scripps Institution of Oceanography (at the University of California- San Diego), University of Nevada-Reno and the University of Colorado went to the region of the Soviet's principal nuclear test site near Semipalatinsk. Together with their Soviet counterparts from the Institute of Physics of the Earth (IPE) in Moscow, they fired off three large chemical explosions. The purpose of these explosions was to demonstrate the sensitivity of the three seismic stations surrounding the test site, to study the efficiency with which high-frequency seismic waves propagate in the region, and to study differences between chemical explosions, nuclear explosions and earthquakes in order more firmly to establish procedures for verification of a nuclear test ban. This paper presents a review of the results of these experiments, an update on the status of the joint project, and a review of the significance of high frequency seismic data to test ban verification

  14. Effluent Containment System for space thermal nuclear propulsion ground test facilities

    International Nuclear Information System (INIS)

    This report presents the research and development study work performed for the Space Reactor Power System Division of the U.S. Department of Energy on an innovative ECS that would be used during ground testing of a space nuclear thermal rocket engine. A significant portion of the ground test facilities for a space nuclear thermal propulsion engine are the effluent treatment and containment systems. The proposed ECS configuration developed recycles all engine coolant media and does not impact the environment by venting radioactive material. All coolant media, hydrogen and water, are collected, treated for removal of radioactive particulates, and recycled for use in subsequent tests until the end of the facility life. Radioactive materials removed by the treatment systems are recovered, stored for decay of short-lived isotopes, or packaged for disposal as waste. At the end of the useful life, the facility will be decontaminated and dismantled for disposal

  15. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    Energy Technology Data Exchange (ETDEWEB)

    Michael Kruzic

    2007-09-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  16. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D and D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release

  17. Effluent Containment System for space thermal nuclear propulsion ground test facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This report presents the research and development study work performed for the Space Reactor Power System Division of the U.S. Department of Energy on an innovative ECS that would be used during ground testing of a space nuclear thermal rocket engine. A significant portion of the ground test facilities for a space nuclear thermal propulsion engine are the effluent treatment and containment systems. The proposed ECS configuration developed recycles all engine coolant media and does not impact the environment by venting radioactive material. All coolant media, hydrogen and water, are collected, treated for removal of radioactive particulates, and recycled for use in subsequent tests until the end of the facility life. Radioactive materials removed by the treatment systems are recovered, stored for decay of short-lived isotopes, or packaged for disposal as waste. At the end of the useful life, the facility will be decontaminated and dismantled for disposal.

  18. On the infrasound detected from the 2013 and 2016 DPRK's underground nuclear tests

    Science.gov (United States)

    Assink, J. D.; Averbuch, G.; Smets, P. S. M.; Evers, L. G.

    2016-04-01

    The underground nuclear tests by the Democratic People's Republic of Korea (DPRK) generated atmospheric infrasound both in 2013 and 2016. Clear detections were made in the Russian Federation (I45RU) and Japan (I30JP) in 2013 at stations from the International Monitoring System. Both tropospheric and stratospheric refractions arrived at the stations. In 2016, only a weak return was potentially observed at I45RU. Data analysis and propagation modeling show that the noise level at the stations and the stratospheric circumpolar vortex were different in 2016 compared to 2013. As the seismic magnitude of the 2013 and 2016 nuclear test explosions was comparable, we hypothesize that the 2016 test occurred at least 1.5 times deeper. In such a case, less seismic energy would couple through the lithosphere-atmosphere interface, leading to less observable infrasound. Since explosion depth is difficult to estimate from seismic data alone, this motivates a synergy between seismics and infrasonics.

  19. Test programme for the nuclear fuel of the Jules Horowitz reactor starts

    International Nuclear Information System (INIS)

    In Cadarache in the south of France, an advanced material test reactor is currently being built. The Jules Horowitz reactor is an initiative of the French Atomic Energy Commission ((CEA), supported by the European Commission and research centres in the Czech Republic, Spain, Finland and Belgium, plus a number of large energy companies. On the request of CEA, SCK-CEN started characterising the nuclear fuel for this reactor, in its own BR2. The article describes SCK-CEN's programme on the characterisation of new nuclear fuel elements.

  20. Chemical Reactivity Testing for the National Spent Nuclear Fuel Program. Quality Assurance Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Newsom, H.C.

    1999-01-24

    This quality assurance project plan (QAPjP) summarizes requirements used by Lockheed Martin Energy Systems, Incorporated (LMES) Development Division at Y-12 for conducting chemical reactivity testing of Department of Energy (DOE) owned spent nuclear fuel, sponsored by the National Spent Nuclear Fuel Program (NSNFP). The requirements are based on the NSNFP Statement of Work PRO-007 (Statement of Work for Laboratory Determination of Uranium Hydride Oxidation Reaction Kinetics.) This QAPjP will utilize the quality assurance program at Y-12, QA-101PD, revision 1, and existing implementing procedures for the most part in meeting the NSNFP Statement of Work PRO-007 requirements, exceptions will be noted.