DOCSLIB.ORG

Nuclear Science and Technology

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Nuclear Science and Technology ISSN 1810-5408 Nuclear Science and Technology Volume 4, Number 1, March 2014 Special issue for the 30th anniversary of the inauguration of the restoration and expansion of Dalat nuclear research reactor (20 March 1984 - 20 March 2014) Published by VIETNAM ATOMIC ENERGY SOCIETY NUCLEAR SCIENCE AND TECHNOLOGY Volume 4, Number 1, March 2014 Editorial Board Editor-in-chief Tran Huu Phat (VINATOM) Executive Editors Vuong Huu Tan (VARANS) Le Van Hong (VINATOM) Cao Đình Thanh (VINATOM) Editors Ngo Quang Huy (HUI) Phan Sy An (HMU) Le Hong Khiem (IOP) Cao Chi (VINATOM) Dao Tien Khoa (VINATOM) Nguyen Nhi Dien (VINATOM) Do Ngoc Lien (VINATOM) Bui Dieu (NCI) Dang Duc Nhan (VINATOM) Le Ngoc Ha (Tran Hung Dao Hospital) Nguyen Mong Sinh (VINATOM) Duong Ngoc Hai (IOM) Le Xuan Tham (DOST of Lamdong) Le Huy Ham (VAAS) Tran Duc Thiep (IOP) Nguyen Quoc Hien (VINATOM) Le Ba Thuan (VINATOM) Bui Hoc (HUMG) Huynh Van Trung (VINATOM) Nguyen Phuc (VINATOM) Dang Thanh Luong (VARANS) Nguyen Tuan Khai (VINATOM) Nguyen Thi Kim Dung (VINATOM) Hoang Anh Tuan (VAEA) Pham Dinh Khang (VINATOM) Foreign Editors Hideki Namba (JAEA, Japan) Pierre Darriulat (INST) Philippe Quentin (CENBG, CNRS, France) Myung Chul Lee (WFNM) Yang (KAERI, Korea) IU.E.Ponionzkevich (DUBNA , Russia) Kato Yasuyoshi (TIT, Japan) Managing Secretary Nguyen Trong Trang (VINATOM) Science Secretary Hoang Sy Than (VINATOM) .................................................................................................................................................................................................................... Copyright: ©2008 by the Vietnam Atomic Energy Society (VAES), Vietnam Atomic Energy Institute (VINATOM). Pusblished by Vietnam Atomic Energy Society, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-4-39420463 Fax: 84-4-39424133 Email: [email protected] Vietnam Atomic Energy Institute, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-4-39420463 Fax: 84-4-39422625 Email: [email protected] .................................................................................................................................................................................................................... Contents Results of Operation and Utilization of the Dalat Nuclear Research Reactor Nguyen Nhi Dien, Luong Ba Vien, Le Vinh Vinh, Duong Van Dong, Nguyen Xuan Hai, Pham Ngoc Son, Cao Dong Vu..............................................................................................1 Design Analyses for Full Core Conversion of The Dalat Nuclear Research Reactor Luong Ba Vien, Le Vinh Vinh, Huynh Ton Nghiem, Nguyen Kien Cuong........................10 Conceptual Nuclear Designof a 20 MW Multipurpose Research Reactor Nguyen Nhi Dien, Huynh Ton Nghiem, Le Vinh Vinh, Vo Doan Hai Dang, Seo Chulgyo, Park Cheol, Kim Hak Sung..................................................................................................26 Some Main Results of Commissioning of The Dalat Research Reactor with Low Enriched Fuel Nguyen Nhi Dien, Luong Ba Vien, Pham Van Lam, Le Vinh Vinh, Huynh Ton Nghiem, Nguyen Kien Cuong, Nguyen Minh Tuan, Nguyen Manh Hung, Pham Quang Huy, Tran Quoc Duong, Vo Doan Hai Dang, Trang Cao Su, Tran Tri Vien...............................36 Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor Duong Van Dong, Pham Ngoc Dien, Bui Van Cuong, Mai Phuoc Tho, Nguyen Thi Thu, Vo Thi Cam Hoa..................................................................................................................46 The gamma two-step cascade method at Dalat Nuclear Research Reactor Vuong Huu Tan, Pham Dinh Khang, Nguyen Nhi Dien, Nguyen Xuan Hai, Tran Tuan Anh, Ho Huu Thang, Pham Ngoc Son, Mangengo Lumengano..........................................57 Progress of Filtered Neutron Beams Development and Applications at the Horizontal Channels No.2 and No.4 of Dalat Nuclear Research Reactor Vuong Huu Tan, Pham Ngoc Son, Nguyen Nhi Dien, Tran Tuan Anh, Nguyen Xuan Hai….62 Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel C.D. Vu, T.Q. Thien, H.V. Doanh, P.D. Quyet, T.T.T. Anh, N.N. Dien.............................70 Some results of NAA collaborative study in white rice performed at Dalat Nuclear Research Institute T.Q. Thien*, C.D. Vu, H.V. Doanh, N.T. Sy........................................................................76 A new rapid neutron activation analysis system at Dalat nuclear research reactor H.V. Doanh, C.D. Vu, T.Q. Thien, P.N. Son, N.T. Sy, N. Giang, N.N. Dien.....................84 Nuclear Science and Technology, Vol. 4, No. 1 (2014), pp. 01-09 Results of Operation and Utilization of the Dalat Nuclear Research Reactor Nguyen Nhi Dien, Luong Ba Vien, Le Vinh Vinh, Duong Van Dong, Nguyen Xuan Hai, Pham Ngoc Son, Cao Dong Vu Nuclear Research Institute (NRI), Vietnam Atomic Energy Institute (VINATOM) 01 Nguyen Tu Luc, Dalat, Vietnam (Received 5 March 2014, accepted 26 March 2014) Abstract: The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20th March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training. During the last 30 years of operation, the DNRR was efficiently utilized for producing many kinds of radioisotopes and radiopharmaceuticals used in nuclear medicine centers and other users in industry, agriculture, hydrology and scientific research; developing a combination of nuclear analysis techniques (INAA, RNAA, PGNAA) and physic-chemical methods for quantitative analysis of about 70 elements and constituents in various samples; carrying out experiments on the reactor horizontal beam tubes for nuclear data measurement, neutron radiography and nuclear structure study; and establishing nuclear training and education programs for human resource development. This paper presents the results of operation and utilization of the DNRR. In addition, some main reactor renovation projects carried out during the last 10 years are also mentioned in the paper. Keywords: DNRR, HEU, LEU, RRRFR, RERTR, WWR-M2, NAA, INAA, RNAA, PGNAA. I. INTRODUCTION converted from HEU to Low Enriched Uranium (LEU) with 19.75% enrichment in The DNRR is a 500-kW pool-type September 2007. Then, the full core conversion reactor loaded with the Soviet WWR-M2 fuel of the reactor to LEU fuel was also performed assemblies. It was reconstructed and upgraded from 24th November 2011 to 13th January 2012. from the USA 250-kW TRIGA Mark-II reactor Recently, the DNRR has been operated with a built in early 1960s. The first criticality of the core configuration loaded with 92 WWR-M2 st renovated reactor was on the 1 November LEU fuel assemblies and 12 beryllium rods 1983 and its regular operation at nominal around the neutron trap. power of 500 kW has been since March 1984. The first fresh core was loaded with 88 fuel The reactor is used as a neutron source assemblies enriched to 36% (HEU- Highly for the purposes of radioisotopes production, Enriched Uranium). neutron activation analysis, basic and applied researches and training. As a unique research In the framework of the program on reactor in Vietnam, the DNRR has been Russian Research Reactor Fuel Return playing an important role in the research and (RRRFR) and the program on Reduced development of nuclear technique applications Enrichment for Research and Test Reactor as well as in nuclear power programme (RERTR), the DNRR core was partly development of the country. Safe operation and ©2014 Vietnam Atomic Energy Society and Vietnam Atomic Energy Institute RESULTS OF OPERATION AND UTILIZATION OF THE DALAT NUCLEAR RESEARCH REACTOR effective utilization of the reactor expected at some main reactor renovation projects carried least to the year 2030 are a long-term objective out during the last 10 years are also of the DNRR. For this reason, so far the mentioned, too. Government has strongly supported for many specific projects in order to upgrade the facility II. BRIEF REACTOR DESCRIPTION and improve its operation and utilization. AND IT’S OPERATION The results of operation and utilization Main specifications of the DNRR are of the DNRR are presented in this paper and shown in Table I. Table I. Specifications of the DNRR. Reactor type Swimming pool TRIGA Mark II, modified to Russian type of IVV-9 Nominal thermal power 500 kW, steady state Coolant and moderator Light water Core cooling mechanism Natural convection Reflector Beryllium and graphite Fuel types WWR-M2, dispersed UO2-Al with 19.75% enrichment, aluminium cladding Number of control rods 7 (2 safety rods, 4 shim rods, 1 regulating rod) Materials of control rods B4C for safety and shim rods, stainless steel for automatic regulating rod Neutron measuring channels 6 combined in 3 housings with 1 CFC and 1 CIC each Vertical irradiation channels 4 (neutron trap, 1 wet channel, 2 dry channels) and 40 holes at the rotary rack Horizontal beam-ports 4 (1 tangential - No #3 and 3 radial - No #1, #2, #4) Thermal column 1 13 -2 -1 Maximum thermal neutron 2.1x10 n.cm .s (in the neutron trap at core center) flux Main utilizations RI, NAA, PGNAA, NR, basic and applied researches, nuclear training The reactor consists of a cylindrical increase the cooling efficiency
Load more

Recommended publications
  • A Low Cost Supercritical Nuclear + Coal 3.0 Gwe Power Plant
    n. 461 August 2012 A low cost supercritical Nuclear + Coal 3.0 Gwe power plant Pedro Cosme Costa Vieira 1 1 FEP-UP, School of Economics and Management, University of Porto A low cost supercritical Nuclear + Coal 3.0 Gwe power plant. Pedro Cosme Costa Vieira, [email protected] Faculdade de Economia do Porto, R. Dr. Roberto Frias, 80, 4200-464 Porto, Portugal Abstract: The rapid growth in the consumption of electricity in China and India has been covered at 80% by coal, which has the side effect of emitting CO2 to the atmosphere. The alternative is the use of nuclear energy that, to become unquestionably competitive, must use supercritical water as coolant. The problem is that the inflow temperature of a supercritical turbine must be at least 500 ºC that is impossible to attain using the mainstream PWR and it is uneconomical to accomplish in a pressure tubes similar to the CANDU and the RBMK reactors. In this paper, I propose a simple but important innovation that is the coupling of the nuclear reactor to a coal fired heater. With this apparently small improvement, it becomes feasible to build a multi-tube slightly supercritical pressure light water reactor where the outflow low temperature of the nuclear reactor, ≤ 400 ºC, results in a simple nuclear reactor. The design I propose will originate a 50% decrease in the cost of the electricity produced using nuclear energy. Keywords: Electricity production, Supercritical water reactor, Nuclear energy, Coal fired plant, Multi-tube reactor, SCWR. 1. Introduction. Every candidate to the Miss Universe Contest whishes to contribute for the end of war and starvation all over the World, above all, when child are the victims.
    [Show full text]
  • Full Core Conversion and Operational Experience with LEU Fuel of the DALAT Nuclear Research Reactor
    RERTR 2014 – 35TH INTERNATIONAL MEETING ON REDUCED ENRICHMENT FOR RESEARCH AND TEST REACTORS OCTOBER 12-16, 2014 IAEA VIENNA INTERNATIONAL CENTER VIENNA, AUSTRIA Full Core Conversion and Operational Experience with LEU Fuel of the DALAT Nuclear Research Reactor NGUYEN, Nhi Dien – LUONG, Ba Vien – LE, Vinh Vinh – HUYNH, Ton Nghiem – NGUYEN, Kien Cuong Reactor Center - Dalat Nuclear Research Institute – Vietnam Atomic Energy Institute 01 Nguyen Tu Luc St, P.O.Box 61100, Dalat, Lamdong – Vietnam ABSTRACT After successful in full core conversion from HEU to LEU fuel at the end of 2011, safe operation and utilization of the Dalat Nuclear Research Reactor (DNRR) was emphasized and improved. During carrying out commissioning program for reactor start up, reactor characteristics parameters were measured and compared with design calculated data. Good agreement between experimental data and calculated data was archived and the working core has met all safety and exploiting requirements. Fuel and in-core management of LEU core were implemented by using MCNP-REBUS linkage computers code system with visual interface to make friendly using. The neutron trap was modified to serve for producing I-131 by increasing 6 containers. Other irradiation channels inside the reactor core and horizontal beam tubes are being effectively used for neutron activation analysis, fundamental research, nuclear data measurement, neutron radiography and nuclear structure study. 1. Introduction Physics and energy start-up of the Dalat Nuclear Research Reactor (DNRR) for full core conversion to low enriched uranium (LEU) fuel were performed from November 24th, 2011 until January 13th, 2012. The program provides specific instructions for manipulating fuel assemblies (FAs) loading in the reactor core and denotes about procedures for carrying out measurements and experiments during physics and energy start-up stages to guarantee that loaded LEU FAs in the reactor core are in accordance with calculated loading diagram and implementation necessary measurements to ensure for safety operation of DNRR.
    [Show full text]
  • Advances in Small Modular Reactor Technology Developments
    Advances in Small Modular Reactor Technology Developments Advances in Small Modular Reactor Technology Developments Technology in Small Modular Reactor Advances A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2018 Edition For further information: Nuclear Power Technology Development Section (NPTDS) Division of Nuclear Power IAEA Department of Nuclear Energy International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna, Austria Telephone: +43 1 2600-0 Fax: +43 1 2600-7 Email: [email protected] Internet: http://www.iaea.org Printed by IAEA in Austria September 2018 18-02989E ADVANCES IN SMALL MODULAR REACTOR TECHNOLOGY DEVELOPMENTS 2018 Edition A Supplement to: IAEA Advanced Reactors Information System (ARIS) http://aris.iaea.org DISCLAIMER This is not an official IAEA publication. The material has not undergone an official review by the IAEA. The views expressed do not necessarily reflect those of the International Atomic Energy Agency or its Member States and remain the responsibility of the contributors. Although great care has been taken to maintain the accuracy of information contained in this publication, neither the IAEA nor its Member States assume any responsibility for consequences which may arise from its use. The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.
    [Show full text]
  • Isotopes of Iodine 1 Isotopes of Iodine
    Isotopes of iodine 1 Isotopes of iodine There are 37 known isotopes of iodine (I) from 108I to 144I, but only one, 127I, is stable. Iodine is thus a monoisotopic element. Its longest-lived radioactive isotope, 129I, has a half-life of 15.7 million years, which is far too short for it to exist as a primordial nuclide. Cosmogenic sources of 129I produce very tiny quantities of it that are too small to affect atomic weight measurements; iodine is thus also a mononuclidic element—one that is found in nature essentially as a single nuclide. Most 129I derived radioactivity on Earth is man-made: an unwanted long-lived byproduct of early nuclear tests and nuclear fission accidents. All other iodine radioisotopes have half-lives less than 60 days, and four of these are used as tracers and therapeutic agents in medicine. These are 123I, 124I, 125I, and 131I. Essentially all industrial production of radioactive iodine isotopes A Pheochromocytoma is seen as a involves these four useful radionuclides. dark sphere in the center of the body The isotope 135I has a half-life less than seven hours, which is too short to be (it is in the left adrenal gland). Image is by MIBG scintigraphy, with used in biology. Unavoidable in situ production of this isotope is important in radiation from radioiodine in the 135 nuclear reactor control, as it decays to Xe, the most powerful known neutron MIBG. Two images are seen of the absorber, and the nuclide responsible for the so-called iodine pit phenomenon. same patient from front and back.
    [Show full text]
  • Development of 3-D Neutronic Kinetic Model and Control for CANDU Reactors
    Western University Scholarship@Western Electronic Thesis and Dissertation Repository 10-1-2012 12:00 AM Development of 3-D Neutronic Kinetic Model and Control for CANDU Reactors Lingzhi Xia The University of Western Ontario Supervisor Jin Jiang The University of Western Ontario Graduate Program in Electrical and Computer Engineering A thesis submitted in partial fulfillment of the equirr ements for the degree in Doctor of Philosophy © Lingzhi Xia 2012 Follow this and additional works at: https://ir.lib.uwo.ca/etd Part of the Electrical and Computer Engineering Commons Recommended Citation Xia, Lingzhi, "Development of 3-D Neutronic Kinetic Model and Control for CANDU Reactors" (2012). Electronic Thesis and Dissertation Repository. 898. https://ir.lib.uwo.ca/etd/898 This Dissertation/Thesis is brought to you for free and open access by Scholarship@Western. It has been accepted for inclusion in Electronic Thesis and Dissertation Repository by an authorized administrator of Scholarship@Western. For more information, please contact [email protected]. Development of 3-D Neutronic Kinetic Model and Control for CANDU Reactors (Thesis format: Monograph) By Lingzhi Xia Graduate Program in Electrical and Computer Engineering A thesis submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy School of Graduate and Postdoctoral Studies The University of Western Ontario London, Ontario © Lingzhi Xia, 2012 THE UNIVERSITY OF WESTERN ONTARIO SCHOOL OF GRADUATE AND POSTDOCTORAL STUDIES CERTIFICATE OF EXAMINATION Chief Advisor Examining Board __________________________ Dr. Jin Jiang Dr. Eleodor Nichita Advisory Committee __________________________ __________________________ Dr. Sree Ram Valluri Dr. Ken McIsaac __________________________ __________________________ Dr. Ken McIsaac Dr.
    [Show full text]
  • Nuclear Weapons and Civilian Nuclear Power – Two Dangerous Interdependent Peas in a Pod #2.3 by Chuck Broscious
    Environmental Defense Institute www.environmental-defense-institute.org Nuclear Weapons and Civilian Nuclear Power – Two Dangerous Interdependent Peas in a Pod #2.3 by Chuck Broscious Summary This report draws from numerous sources to show the interdependence between nuclear weapons and civilian nuclear power. The US government’s need to have nuclear power around to keep the perception of “the peaceful atom” and maintain the infrastructure (technical knowledge base, uranium mining, processing, fuel manufacturing and waste management) that are the same for both. Thus subsidies for nuclear power also support nuclear weapons and are available to mitigate maintaining an irrationally huge nuclear bomb infrastructure. There is no shortage of credible opposition to nuclear weapons and separately civilian nuclear power but few make the connection with the two. 1 This connection is crucial to strengthen the argument for opposition for both nuclear weapons and commercial nuclear power because both threaten basic human existence; one by immediate annihilation or nuclear winter; and the other by accident (Fukushima) and/or by diverting resources away from sustainable renewable power sources essential to preventing the existential looming climate disaster. 2 This paper can only focus on Idaho’s involvement within this larger national process and will leave the bigger picture to others. The government recognized from the very beginning of the nuclear age the need to convince the public about the “atoms for peace” via promoting commercial nuclear power. This government promotion uses numerous means at the local level that include charitable giving, community outreach 3, university grants, transfer of nuclear technology 4 and subsidies to the private sector nuclear power generators that make an otherwise uneconomic power program marginally feasible.
    [Show full text]
  • Small-Scale Modular Nuclear Power: an Option for Alaska?
    2011 Prepared by the University of Alaska, Alaska Center for Energy and Power and the Institute for Social and Economic Research with funding through the Alaska Energy Authority Small-Scale Modular Nuclear Power: An Option for Alaska? March 2011 Prepared for: Gwen The Alaska Energy Authority 3/15/11 Project Manager: David Lockard, P.E. Prepared by: The University of Alaska Fairbanks, Alaska Center for Energy and Power in partnership with the University of Alaska Anchorage, Institute of Social and Economic Research Contributing Authors: Project Lead: Gwen Holdmann, Director, Alaska Center for Energy and Power, UAF SMR Technology and Barriers to Deployment: Dennis Witmer, Energy Efficiency Evaluations Frank Williams, Director, Arctic Region Supercomputing Center, UAF Dominique Pride, Doctoral Graduate Student, Alaska Center for Energy and Power, UAF Richard Stevens, Master’s Graduate Student, Alaska Center for Energy and Power, UAF Economics: Ginny Fay, Assistant Professor, Institute of Social and Economic Research, UAA Tobias Schwörer, Research Professional, Institute of Social and Economic Research, UAA For additional information or to provide input about this report, please contact: Gwen Holdmann, Director [email protected] Alaska Center for Energy and Power University of Alaska Fairbanks Physical Address: 814 Alumni Drive Mailing Address: PO Box 755910 Fairbanks, AK 99775-5910 THE UNIVERSITY OF ALASKA IS AN AFFIRMATIVE ACTION/EQUAL OPPORTUNITY EMPLOYER AND EDUCATIONAL INSTITUTION. Acknowledgments We sincerely appreciate the time and effort of the numerous Alaskans and nuclear industry experts who met with us and shared information and ideas related to small modular nuclear reactors and applications for Alaska. For their contributions, we specifically would like to thank Mike Harper, Alaska Energy Authority Deputy Director; Craig Welling, Associate Deputy Assistant Secretary, U.S.
    [Show full text]
  • Plutonium Futures Conference Transactions
    LA-13338-C Conference P l u t o n i u m F u t u r e s — T h e S c i e n c e Topical Conference on Plutonium and Actinides Santa Fe, New Mexico (USA) August 25–27, 1997 Sponsored by Los Alamos National Laboratory in cooperation with the American Nuclear Society 4 91 -3 92 -3 93 +3 94 +3 95 +3 96 +3 5 -4 -4 +4 +4 +2 +4 -5 -5 +5 +5 Pa -6 U -5 Np +6 Pu +6 Am Cm Bk Protactinium Uranium Neptunium Plutonium Americium Curium Berkeli 231.0359 238.029 237.0482 (145) (145) (247) (247) ⋅20⋅9⋅2 ⋅21⋅9⋅2 ⋅22⋅9⋅2 ⋅23⋅8⋅2 ⋅23⋅8⋅2 ⋅25⋅9⋅2 ⋅27⋅8⋅2 Conference Los Alamos NATIONAL LABORATORY Transactions Los Alamos National Laboratory is operated by the University of California for the United States Department of Energy under contract W-7405-ENG-36. Plutonium Futures—The Science Conference General Chairs: Bruce Matthews, Los Alamos National Laboratory Paul Cunningham, Los Alamos National Laboratory Organizing Committee and Reviewers: Kyu C. Kim, Los Alamos National Laboratory K. K. S. Pillay, Los Alamos National Laboratory Gerd M. Rosenblatt, Lawrence Berkeley National Laboratory Edward D. Arthur, Los Alamos National Laboratory Allen Hartford, Jr., Los Alamos National Laboratory Amy Longshore, Los Alamos National Laboratory Program Chairs: Kyu C. Kim. Los Alamos National Laboratory K. K. S. Pillay, Los Alamos National Laboratory Program Committee: Gregory R. Choppin, Florida State University Richard A. Bartsch, Texas Tech University Rodney C. Ewing, University of New Mexico Darleane Hoffman, University of California, Berkeley Lawrence Berkeley National Laboratory Lawrence Livermore National Laboratory John R.
    [Show full text]
  • Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities
    XA9746007, ;/ IAEA-TECDOC-990 Nuclear fuel cycle and reactor strategies: Adjusting to new realities Contributed papers International Symposium held in Vienna, 3-6 June 1997 organized by the International Atomic Energy Agency in co-operation with the European Commission, the OECD Nuclear Energy Agency and the Uranium Institute o w Aiomc mwmy December 1997 -07 The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100, in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the INIS Clearinghouse. The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria NUCLEAR FUEL CYCLE AND REACTOR STRATEGIES: ADJUSTING TO NEW REALITIES CONTRIBUTED PAPERS IAEA, VIENNA, 1997 IAEA-TECDOC-990 ISSN 1011-4289 ©IAEA, 1997 Printed by the IAEA in Austria December 1997 FOREWORD The International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities was held from 3 to 6 June 1997 in Vienna, Austria. It was organized by the International Atomic Energy Agency (IAEA) in co-operation with the European Commission, the Nuclear Energy Agency of the OECD (OECD/NEA) and the Uranium Institute (UI). More than 300 participants from more than 40 countries and 5 organizations took part. The reason for organizing the symposium was to face the new realities in the nuclear fuel cycle and to come to conclusions on how these new realities should be addressed.
    [Show full text]
  • The Impact of Xenon-135 on a Load Following Transatomic Power Molten Salt Reactor
    The Impact of Xenon-135 on a Load Following Transatomic Power Molten Salt Reactor Andrei Rykhlevskii, Daniel O’Grady, Tomasz Kozlowski, Kathryn Huff Advanced Reactors and Fuel Cycles Group University of Illinois at Urbana-Champaign November 19, 2019 Andrei Rykhlevskii Impact of 135Xe on a Load Following TAP MSR 1 / 26 Introduction Load-following Methodology Molten Salt Reactors Results Research objectives Conclusions Outline 1 Introduction Load-following Molten Salt Reactors Motivation Research objectives 2 Methodology Full-core TAP MSR Serpent model Load-following transient 3 Results Multiplication factor dynamics 135Xe/135I balance Neutron spectra 4 Conclusions Andrei Rykhlevskii Impact of 135Xe on a Load Following TAP MSR 2 / 26 Introduction Load-following Methodology Molten Salt Reactors Results Research objectives Conclusions UIUC Project Overview ARPA-E MEITNER Award 1798-1576 PI: Huff Co-PIs: Brooks, Heuser, Kozlowski, Stubbins Objective: This project will establish a xenon removal sparger design to enable load following in liquid-fueled MSRs at ramp rates comparable or superior to ±10% natural gas peaking generation, minute . Motivation • Load following Molten Salt Reactors are potentially transformative • But, feasible online xenon removal system designs are absent. The UIUC project will unlock the benefits of MSRs by bounding these designs • via simulation of multiple physics • fluid dynamics, • neutronics, • and fuel cycle dynamics. • and with novel mass transport and sparging experiments. Andrei Rykhlevskii Impact of 135Xe on a Load Following TAP MSR 3 / 26 Introduction Load-following Methodology Molten Salt Reactors Results Research objectives Conclusions UIUC Project Thrusts Figure 1: In 4 major thrusts the project will establish a feasible design for the sparging system, an overlooked MSR component essential to load following in thermal MSRs.
    [Show full text]
  • Summary Report
    International Atomic Energy Agency IWGGCR/l & IMTBKK1TICNAL WORKING CBODP CE GAS-COOLED REACTORS Specialists Meeting on Gas-cooled Reactor Safety and Licensing Aspects Lausanne, Switzerland 1-3 September I98O SUMMARY REPORT Attention Microfiche User, The original document from which this microfiche was made was found to contain some imperfection or imperfections that reduce full comprehension of some of the text despite the good technical quality of the microfiche itself. The imperfections may he: — missing or illegible pages/figures — wrong pagination — poor overall printing quality, etc. YJe normally refuse to microfiche such a document and request a replacement document (or pages) from the National INIS Centre concerned. However, our experience shows that many months pass before such documents are replaced. Sometimes the Centre is not able to supply a better copy or, in some cases, the pages that were supposed to be missing correspond to a wrong pagination only. We feel that it is better to proceed with distributing the microfiche made of these documents than to withhold them till the imperfections are removed. If the removals are subsequestly made then replacement microfiche can be issued. In line with this approach then, our specific practice for microfiching documents with imperfections is as follows: 1. A microfiche of an imperfect document will be marked with a special symbol (black circle) on the left of the title. This symbol will appear on all masters and copies of the document (1st fiche and trailer fiches) even if the imperfection is on one fiche of the report only. 2. If imperfection is not too general the reason will be specified on a sheet such as this, in the space below.
    [Show full text]
  • 12.2% 116000 120M Top 1% 154 3800
    We are IntechOpen, the world’s leading publisher of Open Access books Built by scientists, for scientists 3,800 116,000 120M Open access books available International authors and editors Downloads Our authors are among the 154 TOP 1% 12.2% Countries delivered to most cited scientists Contributors from top 500 universities Selection of our books indexed in the Book Citation Index in Web of Science™ Core Collection (BKCI) Interested in publishing with us? Contact [email protected] Numbers displayed above are based on latest data collected. For more information visit www.intechopen.com 17 New Sustainable Secure Nuclear Industry Based on Thorium Molten-Salt Nuclear Energy Synergetics (THORIMS-NES) Kazuo Furukawa1, Eduardo D. Greaves2, L. Berrin Erbay3, Miloslav Hron4 and Yoshio Kato5 1Thorium Tech Solution Inc., 2Universidad Simón Bolívar, Caracas, 3Eskişehir Osmangazi University, 4Nuclear research Institute Retz, 5International Thorium Molten-Salt Forum, 1,5Japan 2Venezuela 3Turkey 4Czech Rep. 1. Introduction 1.1 The energy problem In the 21st century the stress due to environmental issues like the greenhouse effect, pollution, desertification, and local climate abnormality, as well as social issues like population explosion (100 M per year), poverty and starvation, may become intolerable, leading to large-scale disorder. However, it seems that there isn’t a more effective measure for averting such disorder and solving human poverty as ensuring an adequate supply of clean and cheap energy. In principle, it is impossible to predict the future. Nevertheless, a hypothetical prediction based on reliable principles, can be quite useful. A future energy scenario based on the initial work of Marchetti [Marchetti 1985, 1987, 1988, 1992], and later modified by the members of the Thorium Molten-Salt Forum [Furukawa, 2006; Furukawa, et al.
    [Show full text]