Technical publications by JAERI staff in 1999, vol. 33

International Nuclear Information System (INIS)

2000-06-01

This list contains 1399 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 1999. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author)

Technical publications by JAERI staff in 2000, vol. 34

International Nuclear Information System (INIS)

2001-04-01

This list contains 830 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 2000. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author)

Manual on JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

1977-05-01

A manual on the revised JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI which complements the library installed for FACOM 230-75 computer. It is subject to further extension in the future, since the present one is still insufficient for scientific calculations. (auth.)

Technical publications by JAERI staff in 1997, vol. 31

International Nuclear Information System (INIS)

1998-06-01

This list contains 998 references published as JAERI technical reports and selected from JAERI personnel's paper in journals and other publications in 1997. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author). 998 refs

Technical publications by JAERI staff in 1998, vol. 32

International Nuclear Information System (INIS)

1999-06-01

This list contains 1074 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 1998. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author). 1074 refs

Manual on JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

1979-11-01

A manual on the revised version of JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI. They are classified into fifteen fields. It is subject to further extension in the future, since there are some fields still insufficient for scientific calculations in the present library. (author)

A comparison of the COG and MCNP codes in computational neutron capture therapy modeling, Part I: boron neutron capture therapy models.

Science.gov (United States)

Culbertson, C N; Wangerin, K; Ghandourah, E; Jevremovic, T

2005-08-01

The goal of this study was to evaluate the COG Monte Carlo radiation transport code, developed and tested by Lawrence Livermore National Laboratory, for neutron capture therapy related modeling. A boron neutron capture therapy model was analyzed comparing COG calculational results to results from the widely used MCNP4B (Monte Carlo N-Particle) transport code. The approach for computing neutron fluence rate and each dose component relevant in boron neutron capture therapy is described, and calculated values are shown in detail. The differences between the COG and MCNP predictions are qualified and quantified. The differences are generally small and suggest that the COG code can be applied for BNCT research related problems.

Modular programming method at JAERI

International Nuclear Information System (INIS)

Asai, Kiyoshi; Katsuragi, Satoru

1982-02-01

In this report the histories, concepts and a method for the construction and maintenance of nuclear code systems of Japan Atomic Energy Research Institute (JAERI) are presented. The method is mainly consisted of novel computer features. The development process of the features and experiences with them which required many man-months and efforts of scientists and engineers of JAERI and a computer manufacturer are also described. One of the features is a file handling program named datapool. The program is being used in code systems which are under development at JAERI. The others are computer features such as dynamic linking, reentrant coding of Fortran programs, interactive programming facility, document editor, quick system output viewer and editor, flexible man-machine interactive Fortran executor, and selective use of time-sharing or batch oriented computer in an interactive porgramming environment. In 1980 JAERI has replaced its two old computer systems by three FACOM M-200 computer systems and they have such features as mentioned above. Since 1981 most code systems, or even big single codes can be changed to modular code systems even if the developers or users of the systems will not recognize the fact that they are using modular code systems. The purpose of this report is to describe our methodology of modular programming from aspects of computer features and some of their applications to nuclear codes to get sympathetic understanding of it from persons of organizations who are concerned with the effective use of computers, especially, in nuclear research fields. (author)

JAERI's activities in JCO accident

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-09-01

The Japan Atomic Energy Research Institute (JAERI) was actively involved in a variety of technical supports and cooperative activities, such as advice on terminating the criticality condition, contamination checks of the residents and consultation services for the residents, as emergency response actions to the criticality accident at the uranium processing facility operated by the JCO Co. Ltd., which occurred on September 30, 1999. These activities were carried out in collaborative ways by the JAERI staff from the Tokai Research Establishment, Naka Fusion Research Establishment, Oarai Research Establishment, and Headquarter Office in Tokyo. As well, the JAERI was engaged in the post-accident activities such as identification of accident causes, analyses of the criticality accident, and dose assessment of exposed residents, to support the Headquarter for Accident Countermeasures of the Science and Technology Agency (STA), the Accident Investigation Committee and the Health Control Committee of the Nuclear Safety Commission of Japan (NSC). This report compiles the activities, that the JAERI has conducted to date, including the discussions on measures for terminating the criticality condition, evaluation of the fission number, radiation monitoring in the environment, dose assessment, analyses of criticality dynamics. (author)

History of the JAERI linac facility for 33 years

International Nuclear Information System (INIS)

Ohkubo, Makio; Mizumoto, Motoharu; Nakajima, Yutaka; Mashiko, Katsuo

1994-01-01

The JAERI electron linear accelerator will be shutdown and disassembled at the end of 1993. At the JAERI, a prototype 20 MeV linac was constructed at 1960, and was used for the neutron time-of-flight experiments and for the isotope productions. An upgraded 120 MeV linac was constructed at 1972, and was used for many fields of research works until 1993. History of the JAERI Linac and the results of the works made using these facilities are reviewed, and also R/D on the accelerator engineering are described briefly. (author)

Commissioning of the JAERI free electron laser

International Nuclear Information System (INIS)

Minehara, E.J.; Nagai, R.; Sawamura, M.

1993-01-01

We have developed, and constructed a prototype for a quasi-cw, and high-average power free electron laser driven by a 15MeV superconducting rf linac at Tokai, JAERI. In designing a high power FEL, there are many available design options to generate the required power output. By applying the superconducting rf linac driver, some of the options relating to the FEL itself may be relaxed by transferring design difficulties to the driver. Because wall losses become minimal in the superconducting accelerator cavity, very long pulse or quasi-cw, and resultant high average power may be readily attained at the JAERI superconducting rf linac FEL. In 1992 Japanese fiscal year, we have successfully demonstrated better cryogenic (stand-by loss<3.5W at 4.5K) and accelerating fields' performances (Eacc=7-9.4MV/m and Q=1-2x10+9) of four JAERI superconducting accelerator modules, and installed them in the FEL accelerator vault. In 1993, Optical resonators and beam transport systems, which have been already assembled, are now under commissioning. A description and the latest results of the JAERI super-conducting rf linac FEL will be discussed in comparison with a normal-conducting one, and reported in the symposium. (author)

Report of the JAERI's Institution Evaluation Committee on general organizational managements

International Nuclear Information System (INIS)

1999-11-01

In accordance with the National Guidelines on the Method of Evaluation for Government R and D, the Institution Evaluation Committee of JAERI conducted the extensive review on overall aspects in the JAERI's organizational management, starting with the Committee Meeting held in December 1998. This report describes the results of the review on 'JAERI's organizational management in view of the National Guidelines', 'Summary of evaluation of R and D themes' and 'Recommendations by the Committee and its Members', The contents, reported to news agencies in March 1999, are also available in the JAERI's internet home page. (author)

Neutron capture therapy. Principles and applications

International Nuclear Information System (INIS)

Sauerwein, Wolfgang A.G.; Moss, Raymond; Wittig, Andrea; Nakagawa, Yoshinobu

2012-01-01

State of the art report on neutron capture therapy. Summarizes the progress made in recent decades. Multidisciplinary approach. Written by the most experienced specialists Neutron capture therapy (NCT) is based on the ability of the non-radioactive isotope boron-10 to capture thermal neutrons with very high probability and immediately to release heavy particles with a path length of one cell diameter. This in principle allows for tumor cell-selective high-LET particle radiotherapy. NCT is exciting scientifically but challenging clinically, and a key factor in success is close collaboration among very different disciplines. This book provides a comprehensive summary of the progress made in NCT in recent years. Individual sections cover all important aspects, including neutron sources, boron chemistry, drugs for NCT, dosimetry, and radiation biology. The use of NCT in a variety of malignancies and also some non-malignant diseases is extensively discussed. NCT is clearly shown to be a promising modality at the threshold of wider clinical application. All of the chapters are written by experienced specialists in language that will be readily understood by all participating disciplines.

JAERI's activities on photon production data

International Nuclear Information System (INIS)

Shibata, Keiichi; Maekawa, Fujio; Niita, Koji

1996-01-01

Summarized are activities on photon production data at JAERI. The activities consists of evaluation of photon production data for JENDL Fusion File, benchmark tests of JENDL and FENDL-1 data, and calculation of photon production data in the framework of the Quantum Molecular Dynamics. The capture cross sections of 12 C and 16 O were evaluated for JENDL Fusion File by taking account of the direct radiative capture calculations obtained by A. Mengoni (ENEA). The presently evaluated data are in good agreement with the measurements of Igashira et al. in the keV region, describing the behaviour of p-wave capture which is in proportion to υ. Photon production data on Fe and Ni were updated for JENDL Fusion File by using a statistical-model calculations. According to the results of benchmark tests, the calculations with the updated data reproduce the integral measurements on gamma-ray heating. Benchmark tests of evaluated photon production data have been continued by analyzing the integral experimental performed at OKTAVIAN and FNS. The calculations with JENDL Fusion File are in good agreement with the integral measurements. Preliminary calculation of photon production data in the high energy region has been done in the framework of the Quantum Molecular Dynamics approach. The quasi-deuteron model was used to describe photon absorption in the low energy region. Above pion production threshold, pion production channels were included in the calculation. The neutron-proton bremsstrahlung obtained with the one-boson-exchange model was incorporated into QMD codes. (Abstract only)

Neutron capture therapy: Years of experimentation---Years of reflection

International Nuclear Information System (INIS)

Farr, L.E.

1991-01-01

This report describes early research on neutron capture therapy over a number of years, beginning in 1950, speaking briefly of patient treatments but dwelling mostly on interpretations of our animal experiments. This work carried out over eighteen years, beginning over forty years ago. Yet, it is only fitting to start by relating how neutron capture therapy became part of Brookhaven's Medical Research Center program

An outcome of nuclear safety research in JAERI. Predominance of research

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki; Kawashima, Kei; Ito, Keishiro; Katsuki, Chisato

2010-02-01

Bibliometric study by means of research papers revealed the followings; (1) Nuclear Safety Research (NSR) performed in Japan is the 2nd highest in the world followed by USA. The share of JAERI for safety paper publication is about 25% in Japan (2) During past 25 years, JAERI is predominant at 39 safety fields out of 97, that is, 40% to the total. This is the fact revealed from comparison of published number of research papers with those of other organizations. (3) JAERI is recently changing its stress point from reactor-oriented accidents to the down stream of nuclear fuel cycling. There existed impact of TMI-2 accident on NSR-JAERI, especially in the field of thermal hydraulics, LOCA, severe accident and risk analysis. (author)

Current status of neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-05-01

There are about 6000 new glioblastoma multiform brain tumours diagnosed each year in the United States of America alone. This cancer is usually fatal within six months of diagnosis even with current standard treatments. Research on boron neutron capture therapy (BNCT) has been considered as a method of potentially curing such cancers. There is a great interest at under-utilised research reactors institutions to identify new medical utilization, attractive to the general public. Neutron capture therapy is a true multidisciplinary topic with a large variety of individuals involved. This publication attempts to provide current information for all those thinking about being involved with NCT, based on the knowledge and experience of those who have pioneered the treatment. It covers the whole range of NCT from designing reactor conversions or new facilities, through to clinical trials and their effectiveness. However, since most work has been done with boron capture therapy for brain tumours using modified thermal research reactors, this tends to be the focus of the report. One of the factors which need to be addressed at the beginning is the timing of the further development of NCT facilities. It should be emphasised that all current work is still at the research stage. Many of those now involved believe that there is little need for many more research facilities until such time as the treatment shows more promising results. For this and other reasons discussed in the report, very serious consideration should be given by research reactor owners and operators before spending large sums of money converting their facilities for NCT.

Current status of neutron capture therapy

International Nuclear Information System (INIS)

2001-05-01

There are about 6000 new glioblastoma multiform brain tumours diagnosed each year in the United States of America alone. This cancer is usually fatal within six months of diagnosis even with current standard treatments. Research on boron neutron capture therapy (BNCT) has been considered as a method of potentially curing such cancers. There is a great interest at under-utilised research reactors institutions to identify new medical utilization, attractive to the general public. Neutron capture therapy is a true multidisciplinary topic with a large variety of individuals involved. This publication attempts to provide current information for all those thinking about being involved with NCT, based on the knowledge and experience of those who have pioneered the treatment. It covers the whole range of NCT from designing reactor conversions or new facilities, through to clinical trials and their effectiveness. However, since most work has been done with boron capture therapy for brain tumours using modified thermal research reactors, this tends to be the focus of the report. One of the factors which need to be addressed at the beginning is the timing of the further development of NCT facilities. It should be emphasised that all current work is still at the research stage. Many of those now involved believe that there is little need for many more research facilities until such time as the treatment shows more promising results. For this and other reasons discussed in the report, very serious consideration should be given by research reactor owners and operators before spending large sums of money converting their facilities for NCT

Development of superconducting cavities at JAERI

International Nuclear Information System (INIS)

Ouchi, N.

2001-01-01

Development of superconducting (SC) cavities is continued for the high intensity proton accelerator in JAERI. In FY-1999, we carried out R and D work; (1) 2nd vertical test of β=0.886 single-cell cavity, (2) vertical test for observation of Q-disease without heat treatment after electropolishing, (3) vertical test of β=0.5 5-cell cavity, (4) pretuning, surface treatment and vertical test of β=0.886 5-cell cavity, (5) pulsed operation of β=0.886 single-cell cavity in the vertical test to confirm the validity of a new model calculation. This paper describes the present status of the R and D work for the SC cavities in JAERI. (author)

Microdosimetry for Boron Neutron Capture Therapy

International Nuclear Information System (INIS)

Maughan, R.L.; Kota, C.

2000-01-01

The specific aims of the research proposal were as follows: (1) To design and construct small volume tissue equivalent proportional counters for the dosimetry and microdosimetry of high intensity thermal and epithermal neutron beams used in BNCT, and of modified fast neutron beams designed for boron neutron capture enhanced fast neutron therapy (BNCEFNT). (2) To develop analytical methods for estimating the biological effectiveness of the absorbed dose in BNCT and BNCEFNT based on the measured microdosimetric spectra. (3) To develop an analytical framework for comparing the biological effectiveness of different epithermal neutron beams used in BNCT and BNCEFNT, based on correlated sets of measured microdosimetric spectra and radiobiological data. Specific aims (1) and (2) were achieved in their entirety and are comprehensively documented in Jay Burmeister's Ph.D. dissertation entitled ''Specification of physical and biologically effective absorbed dose in radiation therapies utilizing the boron neutron capture reaction'' (Wayne State University, 1999). Specific aim (3) proved difficult to accomplish because of a lack of sufficient radiobiological data

Laser isotope separation studies in JAERI

International Nuclear Information System (INIS)

Arisawa, Takashi; Shiba, Koreyuki

1986-01-01

For uranium enrichment, Japan Atomic Energy Research Institute (JAERI) has been studying atomic vapor laser isotope separation since 1976, in addition to such separation methods as gas diffusion, chemical exchange and gas-dynamic techniques. Studies carried out to date in JAERI is briefly summarized in the first part of the report. Then, some major separation techniques which have been studied in JAERI are outlined, and typical results obtained are presented. A large part is devoted to the multiple-photon photoionization technique, which is commonly known as the atomic laser isotope separation method for uranium enrichment. It has such advantages as 1) very high spectral selectivity for the relevant isotope and 2) highly improved photoionizing effect by means of two- and three-step resonance photoionization processes. Here, the atomic laser isotope separation method is discussed in detail with respect to the evaporation process, energy levels, photoionization, selectivity, photoionization schemes, ion recovery, separation in macroscopic amounts, and separation of trace amounts of isotopes. Typical observed and claculated results related to these subjects are shown. In addition, the report briefly describes some other separation processes including laser induced chemical reaction, multiple photo-dissociation, multiple-photo excitation and UV dissociation, laser induced thermal diffusion, and laser centrifugation. (Nogami, K.)

A system of nuclear material accountancy in the JAERI

International Nuclear Information System (INIS)

Kase, Toshio; Nishizawa, Satoshi; Takahashi, Yoshindo

1983-05-01

Pursuant to the domestic law and regulations revised in 1978 as to be conformed to the requirements specified in the Safeguards Agreement under the Non-Proliferation Treaty (NPT), the JAERI's system of nuclear material accountancy has been effectively developed. The system of accountancy in the JAERI is based on the information treatment by the computer. The data of nuclear material are retained batchwisely together with their complicate history reflected the inventory changes and other transactions. The reports represented these data are prepared and submitted to the IAEA through the Government every month. The inspections are frequently conducted to the JAERI to verify the material appeared in the reports. Item counting, item identification and non-destructive assay technique are brought to the verification. In some cases, seals of the Government and the IAEA are applied to the nuclear material at the inspections, as their containment measures. The surveillance camera is also installed in the facility to look whole view of reactor room and spent fuel pond. In this paper, the general safeguards application and its corresponding accountancy system on JAERI's nuclear facility are described. (author)

Manual for JSSL (JAERI Scientific Subroutine Library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Tsutsui, Tsuneo

1991-09-01

JSSL (JAERI Scientific Subroutine Library) is a library of scientific subroutines developed or modified in JAERI. They are classified into sixteen fields (Special Functions, Linear Problems, Eigenvalue and Eigenvector Problems, Non Linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). This report is the user manual for the revised version of JSSL which involves evaluated subroutines selected from the previous compilation of JSSL, applied in almost all the fields. (author)

JAERI Tandem annual report 1983

International Nuclear Information System (INIS)

Harada, Kichinosuke; Maruyama, Michio; Okashita, Hiroshi; Ozawa, Kunio; Shikazono, Naomoto; Tanaka, Shigeya

1984-07-01

This annual report describes research activities which have been performed with JAERI tandem accelerator from April 1, 1983 to March 31, 1984. Summary reports of 32 papers, publications, personnel and a list of co-operative reserches with universities are contained. (author)

JAERI tandem annual report, 1982

International Nuclear Information System (INIS)

Harada, Kichinosuke; Maruyama, Michio; Ozawa, Kunio; Shikazono, Naomoto; Tamura, Tsutomu; Tanaka, Shigeya

1983-06-01

This annual report describes research activities which have been performed with JAERI tandem accelerator from September 1, 1981 to March 31, 1983. Summary reports of 38 papers, publications, personnel and a list of co-operative researches with universities are contained. (author)

Neutron capture therapy for melanoma

Energy Technology Data Exchange (ETDEWEB)

Coderre, J.A.; Glass, J.D.; Micca, P.; Fairchild, R.G.

1988-01-01

The development of boron-containing compounds which localize selectively in tumor may require a tumor-by-tumor type of approach that exploits any metabolic pathways unique to the particular type of tumor. Melanin-producing melanomas actively transport and metabolize aromatic amino acids for use as precursors in the synthesis of the pigment melanin. It has been shown that the boron-containing amino acid analog p-borono-phenylalanine (BPA) is selectively accumulated in melanoma tissue, producing boron concentrations in tumor that are within the range estimated to be necessary for successful boron neutron capture therapy (BNCT). We report here the results of therapy experiments carried out at the Brookhaven Medical Research Reactor (BMRR). 21 refs., 5 figs., 3 tabs.

Neutron capture therapy for melanoma

International Nuclear Information System (INIS)

Coderre, J.A.; Glass, J.D.; Micca, P.; Fairchild, R.G.

1988-01-01

The development of boron-containing compounds which localize selectively in tumor may require a tumor-by-tumor type of approach that exploits any metabolic pathways unique to the particular type of tumor. Melanin-producing melanomas actively transport and metabolize aromatic amino acids for use as precursors in the synthesis of the pigment melanin. It has been shown that the boron-containing amino acid analog p-borono-phenylalanine (BPA) is selectively accumulated in melanoma tissue, producing boron concentrations in tumor that are within the range estimated to be necessary for successful boron neutron capture therapy (BNCT). We report here the results of therapy experiments carried out at the Brookhaven Medical Research Reactor (BMRR). 21 refs., 5 figs., 3 tabs

Atomic and Molecular Data activities at NDC/JAERI

International Nuclear Information System (INIS)

Shirai, Toshizo

2000-01-01

The NDC/JAERI is a member of the international atomic and molecular (A+M) data center network for fusion, coordinated by the International Atomic Energy Agency. In this poster we introduce our Evaluated Atomic and Molecular Data Library (JEAMDL) developed in collaboration with the JAERI Research Committee on A+M Data and with researchers of ORNL and NIST under the US-Japan fusion cooperation program. JEAMDL comprises databases of collision cross section data and of spectroscopic data. We briefly summarize these two databases below. (author)

Status of JAERI tandem accelerator

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Tadashi; Kanda, Susumu; Takeuchi, Suehiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

2001-02-01

JAERI Tandem Accelerator had been operated approximately 230 days in fiscal year of 1999. Meanwhile, we had three times of maintenance period with vent. Total operation-times were 5273 hours. We could not carry out the experiment using rare gas, due to malfunction of the RF power supply for the ECR ion source. The type of the RF power supply is peculiar and it is impossible to get spare parts for repair. We are now investigating the backup RF power supply. The power supply for the magnet became unstable due to degradation of insulation in the shunt resistance, which is used for feedback stabilization. Stability was recovered after cleaning. The acrylic resin shaft was cracked. This cracks have a potential for severe accidents. So far bearing of the shaft has no problem. The reason of cracks may be self-destruction by charge accumulation in the shaft. JAERI Tandem Accelerator is approximately 20 years old. There appear requirements on the higher ion currents for additional ion species. Therefore, authors are investigating cost effective improvement plans of RFQ (Radio Frequency Quadra-pole) and IH type accelerator based on KEK (High Energy Accelerator Research Organization) R and D. As a whole, maintenance services for the control system are increasing due to some changes of computer programs. There are some difficulties to keep skilled personnel for facilities operation. Authors are gradually increasing hired personnel with contract from 1993. However, loads for JAERI permanent staffs are still heavy. It takes much longer time to educate skilled persons especially for safety. (Y. Tanaka)

An outcome of nuclear safety research in JAERI. Case study for LOCA, FP, criticality and reprocessing

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki; Ito, Keishiro; Kawashima, Kei; Katsuki, Chisato; Shirabe, Masashi

2009-09-01

An outcome of nuclear safety research done by JAERI was case studied by the bibliometric method. (1) For LOCA (loss-of-coolant accident) a domestic share of JAERI in monoclinic research paper was 63% at the past (20) 1978-1982 but was decreased to 40% at the present 1998-2002. For co-authored papers a domestic share between JAERI and PS (public sectors) is almost zero at past (20) but increased to 4% at the present. Research cooperation is active between Tokyo University and JAERI or between JAERI and Nagoya University. (2) Project-type research is to have a large monopolization in papers and that of basic-type research is to have a large development of research networking (DRN). (3) For FP, a share of co-authored paper is high due to an enhanced cooperation among JAERI-PO (Public Organization)-PS. For criticality, research activity was enhanced after JCO accident, especially at NUCEF. (4) For reprocessing, PS had a monopolistic position with a domestic share of 71% and a share of JAERI was about 20%. (5) LOCA and RIA outputs born by NSR-JAERI coincided partly to those of the Safety Licensing Guidelines but a share of contribution done by JAERI was ambiguous due to the lack of necessary information. (author)

Accelerator based neutron source for neutron capture therapy

International Nuclear Information System (INIS)

Salimov, R.; Bayanov, B.; Belchenko, Yu.; Belov, V.; Davydenko, V.; Donin, A.; Dranichnikov, A.; Ivanov, A.; Kandaurov, I; Kraynov, G.; Krivenko, A.; Kudryavtsev, A.; Kursanov, N.; Savkin, V.; Shirokov, V.; Sorokin, I.; Taskaev, S.; Tiunov, M.

2004-01-01

Full text: The Budker Institute of Nuclear Physics (Novosibirsk) and the Institute of Physics and Power Engineering (Obninsk) have proposed an accelerator based neutron source for neutron capture and fast neutron therapy for hospital. Innovative approach is based upon vacuum insulation tandem accelerator (VITA) and near threshold 7 Li(p,n) 7 Be neutron generation. Pilot accelerator based neutron source for neutron capture therapy is under construction now at the Budker Institute of Nuclear Physics, Novosibirsk, Russia. In the present report, the pilot facility design is presented and discussed. Design features of facility components are discussed. Results of experiments and simulations are presented. Complete experimental tests are planned by the end of the year 2005

Gadolinium atom on neutron capture therapy

International Nuclear Information System (INIS)

Oda, Y.; Takagaki, M.; Miyatake, S.; Kikuchi, H.

1994-01-01

This report describes our measurements of gadolinium concentrations in several brain tumors obtained from fresh surgical specimens, as compared with corresponding concentrations in the blood. Moreover we tried to find out if the gadolinium concentration is high enough to use this compound in the treatment of brain tumors by neutron capture therapy. (J.P.N.)

Manual for JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Inoue, Shuji; Fujimura, Toichiro; Tsutsui, Tsuneo; Nishida, Takahiko

1982-09-01

A manual on revised version of JAERI scientific subroutine library, which is a collection of scientific subroutines developed or modified in JAERI. They are classified into fifteen fields (Special Functions, Linear Problems, Eigenvalue and Eigen vector Problems, Non linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). Main expansion of this version is in the fields of mathematical programming and statistical functions. The present library may be said to be a comprehensive compilation of scientific subroutines covering almost all the important fields. (author)

Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

International Nuclear Information System (INIS)

1999-09-01

Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-09-01

Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

Advances in neutron capture therapy 2006. Proceedings of 12th international congress on neutron capture therapy

International Nuclear Information System (INIS)

Nakagawa, Yoshinobu; Kobayashi, Tooru; Fukuda, Hiroshi

2006-01-01

The Twelfth International Congress on Neutron Capture Therapy (ICNCT-12) is being held from October 9th to 13th, 2006 at the Kagawa International Congress Hall in Takamatsu, Kagawa, Japan. The main theme of the congress is From the past to the Future'. Five symposiums were organized to accommodate all the contributions from the international scientific committees of the International Society for Neutron Capture Therapy (ISNCT), and two symposiums were added to balance the number of fields of specialties. The seven symposiums for ICNCT-12 are as follows: 1) Clinical Results of BNCT for Brain Tumors, 2) Dosimetry, 3) Treatment Planning system, 4) Drug Delivery System, 5) Biomedical and General Matters, 6) BNCT Systems using Accelerators, 7) New Applications and Protocols for BNCT. There are a total of 195 presentations in this congress: 3 special lectures, 34 symposium presentations, 10 presentations in two special sessions from the recipients of the Ralph G. Fairchild Award, 70 presentations in the oral parallel sessions and 78 presentations in the poster sessions. A compilation of 169 papers are published in this proceedings. The 165 of the presented papers are indexed individually. (J.P.N.)

Clinical considerations for neutron capture therapy of brain tumors

International Nuclear Information System (INIS)

Madoc-Jones, H.; Wazer, D.E.; Zamenhof, R.G.; Harling, O.K.; Bernard, J.A. Jr.

1990-01-01

The radiotherapeutic management of primary brain tumors and metastatic melanoma in brain has had disappointing clinical results for many years. Although neutron capture therapy was tried in the US in the 1950s and 1960s, the results were not as hoped. However, with the newly developed capability to measure boron concentrations in blood and tissue both quickly and accurately, and with the advent of epithermal neutron beams obviating the need for scalp and skull reflection, it should not be possible to mount such a clinical trial of NCT again and avoid serious complications. As a prerequisite, it will be important to demonstrate the differential uptake of boron compound in brain tumor as compared with normal brain and its blood supply. If this can be done, then a trial of boron neutron capture therapy for brain tumors should be feasible. Because boronated phenylalanine has been demonstrated to be preferentially taken up by melanoma cells through the biosynthetic pathway for melanin, there is special interest in a trial of boron neutron capture therapy for metastatic melanoma in brain. Again, the use of an epithermal beam would make this a practical possibility. However, because any epithermal (or thermal) beam must contain a certain contaminating level of gamma rays, and because even a pure neutron beam cases gamma rays to be generated when it interacts with tissue, they think that it is essential to deliver treatments with an epithermal beam for boron neutron capture therapy in fractions in order to minimize the late-effects of low-LET gamma rays in the normal tissue

Status and Future Plans of JAERI Eergy-Recovery Linac FEL

CERN Document Server

Hajima, R; Kikuzawa, N; Minehara, E J; Nagai, R; Nishimori, N; Nishitani, T; Sawamura, M; Yamauchi, T

2005-01-01

An energy-recovery linac for a high-power free-electron laser is in operation at Japan Atomic Energy Research Institute (JAERI). In this paper, we report results of research activities and future plans of JAERI ERL-FEL, which are the construction of FEL transport line, the operation of newly-installed RF controller and IOTs, the development of super-lattice photo cathode.

Neutron capture therapy with thermal neutrons at IRT MIFI

International Nuclear Information System (INIS)

Zajtsev, K.N.; Portnov, A.A.; Savkin, V.A.; Kulakov, V.N.; Khokhlov, V.F.; Shejno, I.N.; Vajnson, A.A.; Kozlovskaya, N.G.; Meshcherikova, V.V.; Mitin, V.N.; Yarmonenko, S.P.

2001-01-01

Combined preclinical investigations into neutron capture therapy are conducted. Malignant melanoma was adopted as the line of investigation; boron-containing and gadolinium-containing preparations were used during the neutron capture therapy working off. Preparations produce secondary varying radiations when used in tumor. Dogs with spontaneous melanoma were used for the experiments. Procedures for the irradiation of dogs by neutron beam as the stage before use for the treatment of oncology patients were finished off; efficiency of neutron beam influence on normal tissues during the irradiation of dogs with melanoma (and without it) in antitumor and side effect sense was estimated [ru

An upgraded version of the nucleon meson transport code: NMTC/JAERI97

Energy Technology Data Exchange (ETDEWEB)

Takada, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yoshizawa, Nobuaki; Kosako, Kazuaki; Ishibashi, Kenji

1998-02-01

The nucleon-meson transport code NMTC/JAERI is upgraded to NMTC/JAERI97 which has new features not only in physics model and nuclear data but also in computational procedure. NMTC/JAERI97 implements the following two new physics models: an intranuclear cascade model taking account of the in-medium nuclear effects and the preequilibrium calculation model based on the exciton one. For treating the nucleon transport process more accurately, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. Other than those physical aspects, a new geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique are implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The resultant NMTC/JAERI97 is tuned to be executed on the UNIX system. This paper explains about the function, physics models and geometry model adopted in NMTC/JAERI97 and guides how to use the code. (author)

US/JAERI calculational benchmarks for nuclear data and codes intercomparison. Article 8

International Nuclear Information System (INIS)

Youssef, M.Z.; Jung, J.; Sawan, M.E.; Nakagawa, M.; Mori, T.; Kosako, K.

1986-01-01

Prior to analyzing the integral experiments performed at the FNS facility at JAERI, both US and JAERI's analysts have agreed upon four calculational benchmark problems proposed by JAERI to intercompare results based on various codes and data base used independently by both countries. To compare codes the same data base is used (ENDF/B-IV). To compare nuclear data libraries, common codes were applied. Some of the benchmarks chosen were geometrically simple and consisted of a single material to clearly identify sources of discrepancies and thus help in analysing the integral experiments

General considerations for neutron capture therapy at a reactor facility

International Nuclear Information System (INIS)

Binney, S.E.

2001-01-01

In addition to neutron beam intensity and quality, there are also a number of other significant criteria related to a nuclear reactor that contribute to a successful neutron capture therapy (NCT) facility. These criteria are classified into four main categories: Nuclear design factors, facility management and operations factors, facility resources, and non-technical factors. Important factors to consider are given for each of these categories. In addition to an adequate neutron beam intensity and quality, key requirements for a successful neutron capture therapy facility include necessary finances to construct or convert a facility for NCT, a capable medical staff to perform the NCT, and the administrative support for the facility. The absence of any one of these four factors seriously jeopardizes the overall probability of success of the facility. Thus nuclear reactor facility management considering becoming involved in neutron capture therapy, should it be proven clinically successful, should take all these factors into consideration. (author)

Neutron spectrum for neutron capture therapy in boron

International Nuclear Information System (INIS)

Medina C, D.; Soto B, T. G.; Baltazar R, A.; Vega C, H. R.

2016-10-01

Glioblastoma multiforme is the most common and aggressive of brain tumors and is difficult to treat by surgery, chemotherapy or conventional radiation therapy. One treatment alternative is the Neutron Capture Therapy in Boron, which requires a beam modulated in neutron energy and a drug with 10 B able to be fixed in the tumor. When the patients head is exposed to the neutron beam, they are captured by the 10 B and produce a nucleus of 7 Li and an alpha particle whose energy is deposited in the cancer cells causing it to be destroyed without damaging the normal tissue. One of the problems associated with this therapy is to have an epithermal neutrons flux of the order of 10 9 n/cm 2 -sec, whereby irradiation channels of a nuclear research reactor are used. In this work using Monte Carlo methods, the neutron spectra obtained in the radial irradiation channel of the TRIGA Mark III reactor are calculated when inserting filters whose position and thickness have been modified. From the arrangements studied, we found that the Fe-Cd-Al-Cd polyethylene filter yielded a ratio between thermal and epithermal neutron fluxes of 0.006 that exceeded the recommended value (<0.05), and the dose due to the capture gamma rays is lower than the dose obtained with the other arrangements studied. (Author)

The JAERI superconducting RF linac-based FELS and THEIR cryogenics

International Nuclear Information System (INIS)

Minehara, Eisuke J.

2003-01-01

In the 21st century, we need a powerful and efficient free-electron laser (FEL) for academic and industrial uses in almost all fields. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, the JAERI FEL group and I have developed an industrial FEL driven by a compact, stand-alone and zero-boil off super-conducting rf linac with an energy-recovery geometry. Our discussions on the JAERI FEL and cryogenics will cover market-requirements for the industrial FELs, some answers from the JAERI compact, stand-alone and zero-boil off cryostat concept and operational experiences over these 9 years, our discovery of the new, highly-efficient, high-power, and ultra-short pulse lasing mode, and the energy-recovery geometry. (author)

Preparation and certification of a uranium isotope certified reference material JAERI-U5

International Nuclear Information System (INIS)

Tamura, Shuzo; Hashitani, Hiroshi

1982-06-01

The Committee on Analytical Chemistry of Nuclear Fuels and Reactor Materials, JAERI had planned to prepare a new reference material, JAERI-U5 for uranium isotopic measurement since 1978. The reference material is composed of 6 samples of different enrichment in the range of 0.2 to 4.5 wt. percents of 235 U. The preparation includes dissolution of raw materials, blending of solutions, precipitation of ammonium diuranate, drying and ignition to U 3 O 8 . A mass-spectrometric collaborative analysis was carried out by well-trained two laboratories in this country, JAERI and PNC. The certified values were decided from the result of the collaborative work. As the measurements were based on NBS SRM's, JAERI-U5 should be called tertiary standard. The materials are packed in bottles of low-potassium-content glass for a possible use in non-destructive gamma-rays spectrometry. The reference material has been distributing from JAERI with a price of yen 140,000 per set (6 samples of 2 g of each) since 1979. (author)

Role of gel dosimeters in boron neutron capture therapy

International Nuclear Information System (INIS)

Khajeali, Azim; Farajollahi, Ali Reza; Khodadadi, Roghayeh; Kasesaz, Yaser; Khalili, Assef

2015-01-01

Gel dosimeters have acquired a unique status in radiotherapy, especially with the advent of the new techniques in which there is a need for three-dimensional dose measurement with high spatial resolution. One of the techniques in which the use of gel dosimeters has drawn the attention of the researchers is the boron neutron capture therapy. Exploring the history of gel dosimeters, this paper sets out to study their role in the boron neutron capture therapy dosimetric process. - Highlights: • Gel dosimeters have been investigated. • Conventional dosimetric proses of BNCT has been investigated. • Role of gel dosimeters in BNCT has been investigated

Neutron Science Project at JAERI

International Nuclear Information System (INIS)

Oyama, Yukio

1998-01-01

Japan Atomic Energy Research Institute, JAERI, is proposing the Neutron Science Project which aims at bringing about scientific and technological innovation in the fields of basic science and nuclear technology for the 21st century, using high intense spallation neutron source. The research areas to be promoted by the project are neutron structural biology, material science, nuclear physics and various technology developments for accelerator-driven transmutation of long-lived radionuclides which are associated with nuclear power generation. JAERI has been carrying out a R and D program for the partitioning and transmutation with the intention to solve the problem of nuclear fuel cycle backend. The accelerator-driven transmutation study is also covered with this program. In the present stage of the project, a conceptual design is being prepared for a research complex utilizing spallation neutrons, including a high intensity pulsed and steady spallation neutron source with 1.5 GeV and 8 MW superconducting proton linac. The idea and facility plan of the project is described, including the status of technological development of the accelerator, target and facilities. (author)

Neutron Science Project at JAERI

Energy Technology Data Exchange (ETDEWEB)

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

1998-03-01

Japan Atomic Energy Research Institute, JAERI, is proposing the Neutron Science Project which aims at bringing about scientific and technological innovation in the fields of basic science and nuclear technology for the 21st century, using high intense spallation neutron source. The research areas to be promoted by the project are neutron structural biology, material science, nuclear physics and various technology developments for accelerator-driven transmutation of long-lived radionuclides which are associated with nuclear power generation. JAERI has been carrying out a R and D program for the partitioning and transmutation with the intention to solve the problem of nuclear fuel cycle backend. The accelerator-driven transmutation study is also covered with this program. In the present stage of the project, a conceptual design is being prepared for a research complex utilizing spallation neutrons, including a high intensity pulsed and steady spallation neutron source with 1.5 GeV and 8 MW superconducting proton linac. The idea and facility plan of the project is described, including the status of technological development of the accelerator, target and facilities. (author)

From neutron science project to J-PARC. From the viewpoint of JAERI

International Nuclear Information System (INIS)

Oyama, Yukio

2006-01-01

Japan Atomic Energy Research Institute (JAERI), at present Japan Atomic Energy Agency (JAEA), has been developing particle accelerators since its establishment in 1956 for obtaining basic data on the neutron. Also reactor-based neutron sciences have been developed at JAERI/JAEA. Under the so-called omega project which was started in 1988, JAERI/JAEA has been conducting researches on Engineering Test Accelerator for the nuclear transmutation and has built a Basic Test Accelerator. In 1996, a special team for neutron science promotion was organized and pushed R and D works on proton accelerators, targets, neutron engineering, radiation safety and so on. Integration of proton accelerator projects at JAERI and KEK (Institute for High Energy Physics) was proposed in 1998, and both institutes agreed to establish a unified proton accelerator facility, J-PARC. JAEA is promoting the industrial application of neutrons. Also the research on nuclear transmutation at J-PARC, which is not endorsed yet, is an essential objective for JAEA. (K.Y.)

LOCA and RIA studies at JAERI

International Nuclear Information System (INIS)

Sugiyama, Tomoyuki; Nagase, Fumihisa; Nakamura, Jinichi; Fuketa, Toyoshi

2004-01-01

To provide a data base for the regulatory guide of light water reactors, behavior of reactor fuels during off-normal and postulated accident conditions such as loss-of-coolant accident (LOCA) and reactivity-initiated accident (RIA) is being studied at the Japan Atomic Energy Research Institute (JAERI). The LOCA program consists of integral thermal shock tests and other separate tests for oxidation rate and mechanical property of fuel claddings. Prior to the tests on irradiated claddings, the tests have been conducted on non-irradiated claddings to examine separate effects of corrosion and hydrogen absorption during reactor operation. The tests on irradiated claddings have recently been started and results have been obtained. As for an RIA study, a series of experiments with high burnup fuel rods is being performed by using pulse irradiation capability of the NSRR. This paper presents recent results obtained from the LOCA and RIA studies at JAERI. (Author)

Development of seismic PSA methodology at JAERI

International Nuclear Information System (INIS)

Muramatsu, K.; Ebisawa, K.; Matsumoto, K.; Oikawa, T.; Kondo, M.

1995-01-01

The Japan Atomic Energy Research Institute (JAERI) is developing a methodology for seismic probabilistic safety assessment (PSA) of nuclear power plants, aiming at providing a set of procedures, computer codes and data suitable for performing seismic PSA in Japan. In order to demonstrate the usefulness of JAERI's methodology and to obtain better understanding on the controlling factors of the results of seismic PSAs, a seismic PSA for a BWR is in progress. In the course of this PSA, various improvements were made on the methodology. In the area of the hazard analysis, the application of the current method to the model plant site is being carried out. In the area of response analysis, the response factor method was modified to consider the non-linear response effect of the building. As for the capacity evaluation of components, since capacity data for PSA in Japan are very scarce, capacities of selected components used in Japan were evaluated. In the systems analysis, the improvement of the SECOM2 code was made to perform importance analysis and sensitivity analysis for the effect of correlation of responses and correlation of capacities. This paper summarizes the recent progress of the seismic PSA research at JAERI with emphasis on the evaluation of component capacity and the methodology improvement of systems reliability analysis. (author)

Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI`s activities in the 1st Japanese-Korean-Russian joint expedition 1994

Energy Technology Data Exchange (ETDEWEB)

Amano, Hikaru; Matsunaga, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yabuuchi, Noriaki

1996-10-01

Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI`s activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

Development of superconducting pulsed poloidal coil in JAERI

International Nuclear Information System (INIS)

Shimamoto, S.; Okuno, K.; Ando, T.; Tsuji, H.

1990-01-01

In the Japan Atomic Energy Research Institute, (JAERI), development work on pulsed superconductors and coils started in 1979, aiming at the demonstration of the applicability of superconducting technologies to pulsed poloidal coils in a fusion reactor. Initially our effort was concentrated mainly on the development of pool-cooled large-current pulsed conductors. Over the past ten years, superconducting technology has made great progress and the forced-flow cooled coil has assumed great importance in the development work. Now the Demo Poloidal Coil Project is in progress in JAERI, and three large forced-flow cooled coils have so far been fabricated and tested. Many improvements have been achieved in ac-loss performance and mechanical characteristics. (author)

Evaluation of nuclear knowledge management: An outcome in JAERI

International Nuclear Information System (INIS)

Yanagisawa, K.

2006-01-01

The author performed an ex post evaluation on the nuclear research of JAERI and revealed that the national funds invested in this field were 4 b$. With aid of NKM, it was revealed that the total outcome was 6 b$, where the creation of nuclear markets for electricity and nuclear facilities was the main stream. This implies that the cost benefit effect is 6 b$/4 b$ = 1.5 (>1). From this, it can be concluded that JAERI contributes not only to technological promotion of nuclear activity but also to the increase of gross domestic product (GDP). (author)

Development and operation of nuclear material accounting system of JAERI

International Nuclear Information System (INIS)

Obata, Takashi; Numata, Kazuyoshi; Namiki, Shinji; Yamauchi, Takahiro

2003-01-01

For the nuclear material accounting system, the mainframe computer had been used in Japan Atomic Energy Research Institute (JAERI). For the purpose of more flexible use and easy operation, the PC base accounting system has been developed since 1999, and operation started from October, 2002. This system consists of the server with the database software and the client PC with original application software. The functions of this system are the input and edit of data, the creation of inspection correspondence data, and creation of a report to the states. Furthermore, it is also possible to create the Web application which used accounting data on a user level by using the programming language. Now, this system is being specialized in JAERI, but it is during a plan to develop as a system which can be also used at other institutions and organization. In the paper, the outline and operating situation of the nuclear material accounting system of JAERI are presented. (author)

Expectations of JAERI on INIS from a viewpoint of socio-economic evaluation

International Nuclear Information System (INIS)

Yanagisawa, K.; Takahashi, S.; Narita, O.; Yonezawa, M.

2004-01-01

Because the taxpayers funded basic scientific researches in JAERI, a feedback of the results to the public is strongly requested by the Japanese government. By using the concept of socio-economic effect, that is, the stimulation and promotion of social interrelations through a formation of networking in basic research, the authors tried to show a kind of feedback. For this purpose, JAERI developed computer code SOCIOECO combined with INIS was used as a main tool and database. The case study was addressed to the Material Science (MS) field in JAERI. It is revealed from the study that a significant formation and development of socio-economic networking is occurring at the emphasized basic research fields (EBRF) of ion irradiation and actinides having a strong relation to nuclear. For actinides a total of 7,237 papers were written in basic research fields, where the share of JAERI over 25 years was 25%, while 52% by public sectors (PS, namely university (U) and governmental sectors (GS)) and 17% by private organizations (PO). Numbers of co-written papers defined as an index of socio-economic networking were increased with time. The growth rate, for example, between JAERI and PS was of order of 3-4% per 25 years, while 8% per recent 5 years. The socio-economic networking described here seems to be useful for showing the feedback occurring from basic research to the public. (author)

Anesthetic management of Boron Neutron Capture Therapy for glioblastoma

International Nuclear Information System (INIS)

Shinomura, T.; Furutani, H.; Osawa, M.; Ono, K.; Fukuda, K.

2000-01-01

General anesthesia was given to twenty-seven patients who received Boron Neutron Capture Therapy (BNCT) under craniotomy at Kyoto University Research Reactor from 1991 to 1999. Special considerations are required for anesthesia. (author)

JAERI TANDEM annual report 2004. April 1, 2004 - March 31, 2005

International Nuclear Information System (INIS)

Ishii, Tetsuro; Takeuchi, Suehiro; Oshima, Masumi; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

2006-01-01

This annual report describes research activities, which have been performed with the JAERI tandem accelerator and its energy booster from April 1, 2004 to March 31, 2005. Summary reports of 48 papers, and lists of publication, personnel and cooperative research with universities are contained. The JAERI (Japan Atomic Energy Research Institute) have been unified with JNC (Japan Nuclear Fuel Cycle Development Institute) and became JAEA (Japan Atomic Energy Agency) on October 1st, 2005. (author)

Burnup credit implementation plan and preparation work at JAERI

International Nuclear Information System (INIS)

Nomura, Y.; Itahara, K.

2001-01-01

Application of the burnup credit concept is considered to be very effective to the design of spent fuel transport and storage facilities. This technology is all the more important when considering construction of the intermediate spent fuel storage facility, which is to be commissioned by 2010 due to increasing amount of accumulated spent fuel in Japan. Until reprocessing and recycling all the spent fuel arising, they will be stored as an energy stockpile until such time as they can be reprocessed. On the other hand, the burnup credit has been partly taken into account for the spent fuel management at Rokkasho Reprocessing Plant, which is to be commissioned in 2005. They have just finished the calibration tests for their burnup monitor with initially accepted several spent fuel assemblies. Because this monitoring system is employed with highly conservative safety margin, it is considered necessary to develop the more rational and simplified method to confirm burnup of spent fuel. A research program has been instituted to improve the present method employed at the spent fuel management system for the Spent Fuel Receiving and Storage Pool of Rokkasho Reprocessing Plant. This program is jointly performed by Japan Nuclear Fuel Limited (JNFL) and JAERI.This presentation describes the current status of spent fuel accumulation discharged from PWR and BWR in Japan and the recent incentive to introduce burnup credit into design of spent fuel storage and transport facilities. This also includes the content of the joint research program initiated by JNFL and JAERI. The relevant study has been continued at JAERI. The results by these research programs will be included in the Burnup Credit Guide Original Version compiled by JAERI. (author)

Boron containing compounds and their preparation and use in neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Gabel, D.

1992-09-01

The present invention pertains to boron containing thiouracil derivatives, their method of preparations, and their use in the therapy of malignant melanoma using boron neutron capture therapy. No Drawings

Concurrent control system for the JAERI tandem accelerator

International Nuclear Information System (INIS)

Hanashima, Susumu; Shozi, Tokio; Shiozaki, Yasuo; Saito, Motoi; Oogane, Yasuo; Sekiguchi, Satoshi.

1994-01-01

A new control system for the JAERI tandem accelerator is constructed. The system utilizes concurrent processing technology with multiprocessor. Transputers are used both for central processor and I/O front end processors. (author)

Present status and future directions of the JAERI superconducting RF linac-based FEL

International Nuclear Information System (INIS)

Minehara, EJ.; Yamauchi, T.; Sugimori, M.; Sawamura, M.; Hajima, R.; Nagai, R.; Kikuzawa, N.; Nishimori, N.; Shizuma, T.

2000-01-01

The JAERI superconducting rf linac based FEL has successfully been lased to produce a 2.34kW FEL light and l00kW electron beam output in quasi continuous wave operation in February 2000. Twice larger output than the present program goal of 1kW was achieved to improve the optical out coupling method in the FEL optical resonator, the electron gun, and the electron beam optics in the JAERI FEL driver. As our next 2 years program goal is the 100kW class FEL light and a few MW class electron beam output in average, quasi continuous wave operation of the light and electron beam will be planned in the JAERI superconducting rf linac based FEL facility. Conceptual and engineering design options needed for such a very high power operation will be discussed to improve and to upgrade the existing facility. Finally, several applications, table-top superconducting rf linac based FELs, and an X-ray FEL R and D will be discussed as a next-five years program at JAERI-FEL laboratory. (author)

JAERI R & D on accelerator-based transmutation under OMEGA program

Energy Technology Data Exchange (ETDEWEB)

Takizuka, T.; Nishida, T.; Mizumoto, M. [Japan Atomic Energy Research Institute, Ibaraki-ken (Japan)] [and others

1995-10-01

The overview of the Japanese long-term research and development program on nuclide partitioning and transmutation, called {open_quotes}OMEGA,{close_quotes} is presented. Under this national program, major R&D activities are being carried out at JAERI, PNC, and CRIEPI. Accelerator-based transmutation study at JAERI is focused on a dedicated transmutor with a subcritical actinide-fueled subcritical core coupled with a spallation target driven by a high intensity proton accelerator. Two types of system concept, solid system and molten-salt system, are discussed. The solid system consists of sodium-cooled tungsten target and metallic actinide fuel. The molten-salt system is fueled with molten actinide chloride that acts also as a target material. The proposed plant transmutes about 250 kg of minor actinide per year, and generates enough electricity to power its own accelerator. JAERI is proposing the development of an intense proton linear accelerator ETA with 1.5 GeV-10 mA beam for engineering tests of accelerator-based transmutation. Recent achievements in the accelerator development are described.

Production of radioisotopic gamma radiation sources in JAERI

International Nuclear Information System (INIS)

Katoh, Hisashi; Kogure, Hiroto; Suzuki, Kyohei

1980-04-01

The present state of production of gamma radiation sources in Japan Atomic Energy Research Institute (JAERI) is described. Sources of 192 Ir, 60 Co and 170 Tm for industrial and 198 Au and 192 Ir for medical applications are produced and delivered routinely by JAERI. Prefabricated assembly targets are irradiated in JRR-2, JRR-3, JRR-4 or JMTR. The irradiated targets are disassembled in a heavy density concrete cave or a lead-shielded cell, depending on the level of radioactivity. The yield of radioactivity in each target is measured with the aid of an ionization chamber. Where necessary, irradiated targets are encapsulated hermetically in capsules of aluminium, stainless steel or other material. The yield of radioactivity is estimated in relation with the burn-up of target nuclide and product nuclide. (author)

Technical publications by JAERI staff from January 1977 to December 1977

International Nuclear Information System (INIS)

1978-11-01

Approximately 430 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1977 to December 1977. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (author)

Technical publications by JAERI staff from January 1976 to December 1976

International Nuclear Information System (INIS)

1977-11-01

Approximately 400 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1976 to December 1976. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

Technical publications by JAERI staff from January 1975 to December 1975

International Nuclear Information System (INIS)

1977-03-01

Approximately 400 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1975 to December 1975. The contents for each entry include the title, language in which it is written, author (s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

Technical publications by JAERI staff from January 1974 to December 1974

International Nuclear Information System (INIS)

1975-03-01

Approximately 370 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1974 to December 1974. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

Citation analysis in JAERI

International Nuclear Information System (INIS)

Nakamoto, Hideshiro; Shimizu, Takehiro.

1982-01-01

For purposes of the acquisition strategy the citation statistics were investigated on the articles which were published by JAERI staff in 1976, '77 and '78. The citations of 14,769 listed in the off-prints of 1,300 were analized by types of Literature, publication year, scattering, and so on. The results show that the occupation of technical reports increased and the lifetime became longer compared with the results of fifteen years ago. The journal ranking list is the important material for the acquisition of journals in our library. (author)

Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1988

International Nuclear Information System (INIS)

1989-01-01

In 1988, this system called 'Common utilization of JAERI facilities' so far was changed to 'Joint research utilizing JAERI facilities', and by evaluating more positively the function of the General Research Center for Nuclear Energy, it has been emphasized to promote and coordinate the joint research among universities centering around the utilization of JAERI facilities. The total number of the research subjects in fiscal year 1988 reached 138, but the results of 120 of them are collected in this book. General joint research is the standard form of the utilization of various facilities that JAERI has opened to common utilization. Cooperation research is to be carried out by concluding research cooperation contracts between university researchers and JAERI researchers, and the facilities which are not opened to common utilization can be used. In the general joint research, the utilization of irradiation such as activation analysis, radiochemistry, irradiation effect, neutron diffraction and so on and the research using beams are mostly carried out, but in the cooperation research, reactor engineering, reactor materials,, nuclear physics measurement and so on are the main subjects. The total number of visitors in one year was 3829 man-day. (K.I.)

Development and operation of the JAERI superconducting energy recovery linacs

Science.gov (United States)

Minehara, Eisuke J.

2006-02-01

The Japan Atomic Energy Research Institute free-electron laser (JAERI FEL) group at Tokai, Ibaraki, Japan has successfully developed one of the most advanced and newest accelerator technologies named "superconducting energy recovery linacs (ERLs)" and some applications in near future using the ERLs. In the text, the current operation and high power JAERI ERL-FEL 10 kW upgrading program, ERL-light source design studies, prevention of the stainless-steel cold-worked stress-corrosion cracking failures and decommissioning of nuclear power plants in nuclear energy industries were reported and discussed briefly as a typical application of the ERL-FEL.

Present status of spallation target development. JAERI/KEK Joint Project

International Nuclear Information System (INIS)

Hino, R.; Kaminaga, M.; Haga, K.

2001-01-01

The Japan Atomic Energy Research Institute (JAERI) and the High Energy Accelerator Research Organization (KEK) are promoting a plan to construct a neutron scattering facility under the JAERI/KEK Joint Project. Design and R and D works are being carried out vigorously for realizing the mercury target system consisting of the mercury target, moderators and reflectors working as a spallation neutron source, as well as a remote handling system for exchanging such components which will be highly irradiated. This report introduces an outline of the present status of design and development activities on the spallation target system. (author)

Monte Carlo based dosimetry and treatment planning for neutron capture therapy of brain tumors

International Nuclear Information System (INIS)

Zamenhof, R.G.; Brenner, J.F.; Wazer, D.E.; Madoc-Jones, H.; Clement, S.D.; Harling, O.K.; Yanch, J.C.

1990-01-01

Monte Carlo based dosimetry and computer-aided treatment planning for neutron capture therapy have been developed to provide the necessary link between physical dosimetric measurements performed on the MITR-II epithermal-neutron beams and the need of the radiation oncologist to synthesize large amounts of dosimetric data into a clinically meaningful treatment plan for each individual patient. Monte Carlo simulation has been employed to characterize the spatial dose distributions within a skull/brain model irradiated by an epithermal-neutron beam designed for neutron capture therapy applications. The geometry and elemental composition employed for the mathematical skull/brain model and the neutron and photon fluence-to-dose conversion formalism are presented. A treatment planning program, NCTPLAN, developed specifically for neutron capture therapy, is described. Examples are presented illustrating both one and two-dimensional dose distributions obtainable within the brain with an experimental epithermal-neutron beam, together with beam quality and treatment plan efficacy criteria which have been formulated for neutron capture therapy. The incorporation of three-dimensional computed tomographic image data into the treatment planning procedure is illustrated

Neutron dosimetry in boron neutron capture therapy

International Nuclear Information System (INIS)

Fairchild, R.G.; Miola, U.J.; Ettinger, K.V.

1981-01-01

The recent development of various borated compounds and the utilization of one of these (Na 2 B 12 H 11 SH) to treat brain tumors in clinical studies in Japan has renewed interest in neutron capture therapy. In these procedures thermal neutrons interact with 10 B in boron containing cells through the 10 B(n,α) 7 Li reaction producing charged particles with a maximum range of approx. 10μm in tissue. Borated analogs of chlorpromazine, porphyrin, thiouracil and deoxyuridine promise improved tumor uptake and blood clearance. The therapy beam from the Medical Research Reactor in Brookhaven contains neutrons from a modified and filtered fission spectrum and dosimetric consequences of the use of the above mentioned compounds in conjunction with thermal and epithermal fluxes are discussed in the paper. One of the important problems of radiation dosimetry in capture therapy is determination of the flux profile and, hence, the dose profile in the brain. This has been achieved by constructing a brain phantom made of TE plastic. The lyoluminescence technique provides a convenient way of monitoring the neutron flux distributions; the detectors for this purpose utilize 6 Li and 10 B compounds. Such compounds have been synthesized specially for the purpose of dosimetry of thermal and epithermal beams. In addition, standard lyoluminescent phosphors, like glutamine, could be used to determine the collisional component of the dose as well as the contribution of the 14 N(n,p) 14 C reaction. Measurements of thermal flux were compared with calculations and with measurements done with activation foils

JAERI FEL applications in nuclear energy industries

International Nuclear Information System (INIS)

Minehara, Eisuke J.

2005-01-01

The JAERI FEL has first discovered the new FEL lasing of 255fs ultra fast pulse, 6-9% high efficiency, 1GW high peak power, a few kilowatts average power, and wide tunability of medium and far infrared wavelength regions at the same time. Using the new lasing and energy-recovery linac technology, we could extend a more powerful and more efficient free-electron laser (FEL) than 10kW and 25%, respectively, for nuclear energy industries, and others. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, we need the efficient and powerful FEL driven by the JAERI compact, stand alone and zero boil-off super-conducting RF linac with an energy-recovery geometry. Our discussions on the FEL will cover the application of non-thermal peeling, cutting, and drilling to prevent cold-worked stress-corrosion cracking failures in nuclear energy and other heavy industries. (author)

JAERI Material Performance Database (JMPD); outline of the system

International Nuclear Information System (INIS)

Yokoyama, Norio; Tsukada, Takashi; Nakajima, Hajime.

1991-01-01

JAERI Material Performance Database (JMPD) has been developed since 1986 in JAERI with a view to utilizing the various kinds of characteristic data of nuclear materials efficiently. Management system of relational database, PLANNER was employed and supporting systems for data retrieval and output were expanded. JMPD is currently serving the following data; (1) Data yielded from the research activities of JAERI including fatigue crack growth data of LWR pressure vessel materials as well as creep and fatigue data of the alloy developed for the High Temperature Gas-cooled Reactor (HTGR), Hastelloy XR. (2) Data of environmentally assisted cracking of LWR materials arranged by Electric power Research Institute (EPRI) including fatigue crack growth data (3000 tests), stress corrosion data (500 tests) and Slow Strain Rate Technique (SSRT) data (1000 tests). In order to improve user-friendliness of retrieval system, the menu selection type procedures have been developed where knowledge of system and data structures are not required for end-users. In addition a retrieval via database commands, Structured Query Language (SQL), is supported by the relational database management system. In JMPD the retrieved data can be processed readily through supporting systems for graphical and statistical analyses. The present report outlines JMPD and describes procedures for data retrieval and analyses by utilizing JMPD. (author)

Annual report on neutron scattering studies in JAERI

International Nuclear Information System (INIS)

Sato, Masatoshi; Nishi, Masakazu; Fujishita, Hideshi; Iizumi, Masashi

1982-07-01

Neutron scattering studies carried out from September 1979 to August 1981 by Division of Physics, JAERI, and universities with JRR-2 and -3 neutron beam facilities are described: 61 summary reports, and a list of publications. (author)

Analysis of Doppler effect with JAERI-Fast set

International Nuclear Information System (INIS)

Takano, Hideki; Matsui, Yasushi.

1977-07-01

Temperature dependence of group cross sections in the JAERI-Fast set versions I, IR, II and IIR has been tested from the analysis of Doppler experiments performed with two different methods. One is Doppler reactivity measurement for the whole core of SEFOR assembly, and the other sample Doppler reactivity measurement for natural UO 2 in FCA assemblies V-1, V-2, VI-1 and VI-2, ZPR-6-7, ZPR-3-47, and ZPPR-2 and 3. Doppler effects were calculated with one- and two-dimensional diffusion 1-st order perturbation code DOPP2D. The results calculated with the JAERI-Fast set versions II and IIR are in good agreement with the experimental ones. In these calculation, resonance heterogeneity effect, stainless-stell buffer effect and plate heterogeneity effect are considered, and these effects contribute significantly to Doppler effect. (auth.)

Control system for JAERI Free Electron Laser

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

1992-01-01

A control system comprising of the personal computers network and the CAMAC stations for the JAERI Free Electron Laser is designed and is in the development stage. It controls the equipment and analyzes the electron and optical beam experiments. The concept and the prototype of the control system are described. (author)

JAERI contribution to the 19th IAEA Fusion Energy Conference

International Nuclear Information System (INIS)

2003-03-01

This report compiles the contributed papers and presentation materials from JAERI to the 19th IAEA Fusion Energy Conference held at Lyon, France, from October 14th to 19th, 2002. The papers describe the recent progress in the experimental research in JT-60U and JFT-2M tokamaks, theoretical studies, fusion technology and R and D for ITER and fusion reactors. Total 32 papers consist of 1 overview talk, 14 oral and 17 poster presentations. Eight papers written by authors from other institutes and universities under collaboration with JAERI are also included. The 40 of the presented papers are indexed individually. (J.P.N.)

Carborane derivative development for boron neutron capture therapy. Final report

International Nuclear Information System (INIS)

Barnum, Beverly A.; Yan Hao; Moore, Roger; Hawthorne, M. Frederick; Baum, Kurt

1999-01-01

Boron Neutron Capture Therapy [BNCT] is a binary method of cancer therapy based on the capture of neutrons by a boron-10 atom [ 10 B]. Cytotoxic 7 Li nuclei and α-particles are emitted, with a range in tissue of 9 and 5 microm, respectively, about one cell diameter. The major obstacle to clinically viable BNCT is the selective localization of 5-30 ppm 10 B in tumor cells required for effective therapy. A promising approach to BNCT is based on hydrophilic boron-rich oligomeric phosphate diesters, or ''trailers'' that have been shown to concentrate selectively in tumor tissue. Examples of these compounds were prepared previously at high cost using an automated DNA synthesizer. Direct synthesis methods are needed for the production of gram-scale quantities for further biological evaluation. The work accomplished as a result of the collaboration between Fluorochem, Inc. and UCLA demonstrates that short oligomers containing at least five carborane units with four phosphodiester linkages can be prepared in substantial quantities. This work was accomplished by the application of standard phosphoramidite coupling chemistry

Concurrent control system for the JAERI tandem accelerator

International Nuclear Information System (INIS)

Hanashima, S.; Shoji, T.; Horie, K.; Tsukihashi, Y.

1992-01-01

Concurrent processing with a multiprocessor system is introduced to the particle accelerator control system region. The control system is a good application in both logical and physical aspects. A renewal plan of the control system for the JAERI tandem accelerator is discussed. (author)

Commissioning of accelerator based boron neutron capture therapy system

International Nuclear Information System (INIS)

Nakamura, S.; Wakita, A.; Okamoto, H.; Igaki, H.; Itami, J.; Ito, M.; Abe, Y.; Imahori, Y.

2017-01-01

Boron neutron capture therapy (BNCT) is a treatment method using a nuclear reaction of 10 B(n, α) 7 Li. BNCT can be deposited the energy to a tumor since the 10 B which has a higher cross-section to a neutron is high is concentrated on the tumor. It is different from conventional radiation therapies that BNCT expects higher treatment effect to radiation resistant tumors since the generated alpha and lithium particles have higher radiological biological effectiveness. In general, BNCT has been performed in research nuclear reactor. Thus, BNCT is not widely applied in a clinical use. According to recent development of accelerator-based boron neutron capture therapy system, the system has an adequate flux of neutrons. Therefore, National Cancer Canter Hospital, Tokyo, Japan is planning to install accelerator based BNCT system. Protons with 2.5 MeV are irradiated to a lithium target system to generate neutrons. As a result, thermal load of the target is 50 kW since current of the protons is 20.0 mA. Additionally, when the accelerator-based BNCT system is installed in a hospital, the facility size is disadvantage in term of neutron measurements. Therefore, the commissioning of the BNCT system is being performed carefully. In this article, we report about the commissioning. (author)

Phantom experiment of depth-dose distributions for gadolinium neutron capture therapy

International Nuclear Information System (INIS)

Matsumoto, T.; Kato, K.; Sakuma, Y.; Tsuruno, A.; Matsubayashi, M.

1993-01-01

Depth-dose distributions in a tumor simulated phantom were measured for thermal neutron flux, capture gamma-ray and internal conversion electron dose rates for gadolinium neutron capture therapy. The results show that (i) a significant dose enhancement can be achieved in the tumor by capture gamma-rays and internal conversion electrons but the dose is mainly due to capture gamma-rays from the Gd(n, γ) reactions, therefore, is not selective at the cellular level, (ii) the dose distribution was a function of strongly interrelated parameters such as gadolinium concentrations, tumor site and neutron beam size (collimator aperture size), and (iii) the Gd-NCT by thermal neutrons appears to be a potential for treatment of superficial tumor. (author)

Design of a boron neutron capture enhanced fast neutron therapy assembly

Energy Technology Data Exchange (ETDEWEB)

Wang, Zhonglu [Georgia Inst. of Technology, Atlanta, GA (United States)

2006-12-01

The use of boron neutron capture to boost tumor dose in fast neutron therapy has been investigated at several fast neutron therapy centers worldwide. This treatment is termed boron neutron capture enhanced fast neutron therapy (BNCEFNT). It is a combination of boron neutron capture therapy (BNCT) and fast neutron therapy (FNT). It is believed that BNCEFNT may be useful in the treatment of some radioresistant brain tumors, such as glioblastoma multiform (GBM). A boron neutron capture enhanced fast neutron therapy assembly has been designed for the Fermilab Neutron Therapy Facility (NTF). This assembly uses a tungsten filter and collimator near the patient's head, with a graphite reflector surrounding the head to significantly increase the dose due to boron neutron capture reactions. The assembly was designed using Monte Carlo radiation transport code MCNP version 5 for a standard 20x20 cm² treatment beam. The calculated boron dose enhancement at 5.7-cm depth in a water-filled head phantom in the assembly with a 5x5 cm² collimation was 21.9% per 100-ppm ¹⁰B for a 5.0-cm tungsten filter and 29.8% for a 8.5-cm tungsten filter. The corresponding dose rate for the 5.0-cm and 8.5-cm thick filters were 0.221 and 0.127 Gy/min, respectively; about 48.5% and 27.9% of the dose rate of the standard 10x10 cm² fast neutron treatment beam. To validate the design calculations, a simplified BNCEFNT assembly was built using four lead bricks to form a 5x5 cm² collimator. Five 1.0-cm thick 20x20 cm² tungsten plates were used to obtain different filter thicknesses and graphite bricks/blocks were used to form a reflector. Measurements of the dose enhancement of the simplified assembly in a water-filled head phantom were performed using a pair of tissue-equivalent ion chambers. One of the ion chambers is loaded with 1000-ppm natural boron (184-ppm ¹⁰B) to measure dose due to boron neutron capture. The

Production of heavy element and search for new isotopes at JAERI-RMS

Energy Technology Data Exchange (ETDEWEB)

Ikuta, Tomohiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-07-01

The new neutron deficient isotope {sup 209}Th and {sup 212}Pa have been produced in heavy ion induced fusion evaporation reactions. The evaporation residues were separated in-flight by the JAERI recoil mass separator (JAERI-RMS). The {alpha}-decay energy of {sup 209}Th and {sup 212}Pa are 8.080(50) MeV and 8.270(30) MeV, respectively. The corresponding half-lives are 3.8{sub -1.5}{sup +6.9} ms and 5.1{sub -1.9}{sup +6.1} ms. (author)

How should the JAERI neutron source be designed?

International Nuclear Information System (INIS)

Watanabe, Noboru

1996-01-01

The importance of a next-generation neutron source in JAERI is discussed. The feasibility and the performances of three types of neutron sources, namely continuous wave spallation source (CWSS), long-pulse spallation source (LPSS) and short-pulse spallation source (SPSS), are compared based on a proposed JAERI accelerator, a superconducting (SC) proton linac (1-1.5 GeV, 25-16 mA in peak current, finally CW). How to realize one of the world's best neutron source using such a linac with a modest beam-current and what type of neutron source is the best for such a linac are the most important current problems. Since the accelerator is not favorable for LPSS due to a lower peak current and there exist serious technical problems for a CWSS target, a short-pulse spallation source would be the best candidate to realize a 5 MW-class SPSS like ESS, provided that the H - -injection to a compressor ring over a long pulse duration (>2 ms) is feasible. (author)

Environmental monitoring activities in JAERI at JCO accident

International Nuclear Information System (INIS)

Yamaguchi, Takenori

2001-01-01

The Japan Atomic Energy Research Institute (JAERI) was involved in a various environmental monitoring activities, such as environmental radiation monitoring by monitoring post and monitoring car, air dust, soil, green vegetables and water sampling and measurements, neutron and gamma radiation dose rate survey around the JCO site for emergency response actions to the JCO accident on September 30, 1999. These activities were performed from Sep. 30 to Oct. 2, and were the initial and first stage activities in the emergency environmental monitoring activities. JAERI has been assigned to the public organization to support the government by Disaster Prevention Fundamental Law. These activities were performed to ensure the public safety to avoid the effluent of the accident. Through the environmental monitoring activities, I recognized that the importance of the accident information to make the best use for the initial environmental monitoring, and the monitoring information exchange is important to perform the effective monitoring activities for taking the early countermeasures such as evacuation to the public. (author)

Annual report of the research works with joint-use JAERI facilities for fiscal 1974

International Nuclear Information System (INIS)

1975-01-01

Results of the research works by national universities with JAERI's (Japan Atomic Energy Research Institute) joint-use facilities for fiscal 1974 are described. Facilities are research reactors, Co-60, Linac, etc. Research results are presented in individual summaries, covering radiation damage and solid state physics, activation analysis and nuclear chemistry, irradiation effects, etc. Results of the joint works with JAERI are also presented similarly. (Mori, K.)

The present status of JAERI OCTOPUS

International Nuclear Information System (INIS)

Yokota, Watalu

1992-01-01

As the ECR ion source of the JAERI AVF Cyclotron, OCTOPUS was installed. An experimental operation was conducted to increase the capability of generating multi-charged ions and to ameliorate the efficiency of beam transport to the cyclotron. In this paper, the brief description of OCTOPUS is given. And the difference of ion generation characteristics depending on the position of the main gas introduction, and the result of emittance measurement are reported. (J.P.N.)

Present and next steps of the JAERI superconducting rf linac based FEL program

International Nuclear Information System (INIS)

Minehara, E.J.; Yamauchi, T.; Sugimoto, M.

2000-01-01

The JAERI superconducting rf linac based FEL has successfully been lased to produce a 0.3 kW FEL light and 100 kW or larger electron beam output in quasi continuous wave operation in 1999. The 1 kW class output as our present program goal will be achieved to improve the optical out coupling method in the FEL optical resonator, the electron gun, and the electron beam optics in the JAERI FEL driver. As our next 5 year program goal is the 100 kW class FEL light and a few tens MW class electron beam output in average, quasi continuous wave operation of the light and electron beam will be planned in the JAERI superconducting rf linac based FEL facility. Conceptual design options needed for such a very high power operation and shorter wavelength light sources will be discussed to improve and to upgrade the exciting facility. (author)

Neutron capture therapy

International Nuclear Information System (INIS)

Jun, B. J.

1998-11-01

The overall state of the art related with neutron capture therapy(NCT) is surveyed. Since the field related with NCT is very wide, it is not intended to survey all related subjects in depth. The primary objective of this report is to help those working for the installation of a NCT facility and a PGNAA(prompt gamma ray neutron activation analysis) system for the boron analysis understand overall NCT at Hanaro. Therefore, while the parts of reactor neutron source and PGNAA are dealt in detail, other parts are limited to the level necessary to understand related fields. For example, the subject of chemical compound which requires intensive knowledge on chemistry, is not dealt as a separated item. However, the requirement of a compound for NCT, currently available compounds, their characteristics, etc. could be understood through this report. Although the subject of cancer treated by NCT is out of the capability of the author, it is dealt focussing its characteristics related with the success of NCT. Each detailed subject is expected to be dealt more detail by specialists in future. This report would be helpful for the researchers working for the NCT to understand related fields. (author). 128 refs., 3 tabs., 12 figs

Publish literature on the research activities using the JMRT (II). Publication as JAERI research reports

Energy Technology Data Exchange (ETDEWEB)

Nagao, Yoshiharu; Ishii, Tadahiko; Niimi, Motoji; Fujiki, Kazuo; Takahashi, Hidetake (eds.) [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

2002-11-01

The published reports on the research and development activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report compiles the title lists and abstracts of reports published by JAERI and survey the trend of the research and development in JAERI using the JMTR. (author)

Published literature on the research activities using the JMRT (II). Publication as JAERI research reports

International Nuclear Information System (INIS)

Nagao, Yoshiharu; Ishii, Tadahiko; Niimi, Motoji; Fujiki, Kazuo; Takahashi, Hidetake

2002-11-01

The published reports on the research and development activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report compiles the title lists and abstracts of reports published by JAERI and survey the trend of the research and development in JAERI using the JMTR. (author)

Recent advances in neutron capture therapy (NCT)

International Nuclear Information System (INIS)

Fairchild, R.G.

1985-01-01

The application of the 10 B(n,α) 7 Li reaction to cancer radiotherapy (Neutron Capture therapy, or NCT) has intrigued investigators since the discovery of the neutron. This paper briefly summarizes data describing recently developed boronated compounds with evident tumor specificity and extended biological half-lives. The implication of these compounds to NCT is evaluated in terms of Therapeutic Gain (TG). The optimization of NCT using band-pass filtered beams is described, again in terms of TG, and irradiation times with these less intense beams are estimated. 24 refs., 3 figs., 3 tabs

Proceedings of the first JAERI-Kansai international workshop on ultrashort-pulse ultrahigh-power lasers and simulation for laser-plasma interactions

International Nuclear Information System (INIS)

1998-03-01

Records of the First JAERI-Kansai International Workshop, which focused on the subject of 'Ultrashort-Pulse Ultrahigh-Power Lasers and Simulation for Laser-Plasma Interactions', are contained in this issue. The First JAERI-Kansai International Workshop was held as Joint ICFA/JAERI-Kansai International Workshop '97 with International Committee for Future Accelerators (ICFA). This report consists of 24 contributed papers. (J.P.N.)

Proceedings of the first JAERI-Kansai international workshop on ultrashort-pulse ultrahigh-power lasers and simulation for laser-plasma interactions

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

Records of the First JAERI-Kansai International Workshop, which focused on the subject of `Ultrashort-Pulse Ultrahigh-Power Lasers and Simulation for Laser-Plasma Interactions`, are contained in this issue. The First JAERI-Kansai International Workshop was held as Joint ICFA/JAERI-Kansai International Workshop `97 with International Committee for Future Accelerators (ICFA). This report consists of 24 contributed papers. (J.P.N.)

Workshop on neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Fairchild, R.G.; Bond, V.P. (eds.)

1986-01-01

Potentially optimal conditions for Neutron Capture Therapy (NCT) may soon be in hand due to the anticipated development of band-pass filtered beams relatively free of fast neutron contaminations, and of broadly applicable biomolecules for boron transport such as porphyrins and monoclonal antibodies. Consequently, a number of groups in the US are now devoting their efforts to exploring NCT for clinical application. The purpose of this Workshop was to bring these groups together to exchange views on significant problems of mutual interest, and to assure a unified and effective approach to the solutions. Several areas of preclinical investigation were deemed to be necessary before it would be possible to initiate clinical studies. As neither the monomer nor the dimer of sulfhydryl boron hydride is unequivocally preferable at this time, studies on both compounds should be continued until one is proven superior.

Workshop on neutron capture therapy

International Nuclear Information System (INIS)

Fairchild, R.G.; Bond, V.P.

1986-01-01

Potentially optimal conditions for Neutron Capture Therapy (NCT) may soon be in hand due to the anticipated development of band-pass filtered beams relatively free of fast neutron contaminations, and of broadly applicable biomolecules for boron transport such as porphyrins and monoclonal antibodies. Consequently, a number of groups in the US are now devoting their efforts to exploring NCT for clinical application. The purpose of this Workshop was to bring these groups together to exchange views on significant problems of mutual interest, and to assure a unified and effective approach to the solutions. Several areas of preclinical investigation were deemed to be necessary before it would be possible to initiate clinical studies. As neither the monomer nor the dimer of sulfhydryl boron hydride is unequivocally preferable at this time, studies on both compounds should be continued until one is proven superior

JAERI TIARA annual report vol. 2 (1992)

International Nuclear Information System (INIS)

Ishigaki, Isao; Tanaka, Ryuichi; Nashiyama, Isamu; Naramoto, Hirosi; Omichi, Hideki; Toraishi, Akio; Watanabe, Hiromasa; Watanabe, Hiroshi

1993-12-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1992 to March 31, 1993. Summary reports of 60 papers and brief descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

Medical and biological requirements for boron neutron capture therapy

International Nuclear Information System (INIS)

Gahbauer, R.; Goodman, J.H.; Kanellitsas, C.; Clendenon, N.; Blue, J.

1986-01-01

In conventional radiation therapy, tumor doses applied to most solid tumors are limited by the tolerance of normal tissues. The promise of Boron Neutron Capture Therapy lies in its potential to deposit high doses of radiation very specifically to tumor tissue. Theoretically ratios of tumor to normal tissue doses can be achieved significantly higher than conventional radiotherapeutic techniques would allow. Effective dose distributions obtainable are a complex function of the neutron beam characteristics and the macro and micro distributions of boron in tumor and normal tissues. Effective RBE doses are calculated in tumors and normal tissue for thermal, epithermal and 2 keV neutrons

Construction of new critical experiment facilities in JAERI

International Nuclear Information System (INIS)

Takeshita, Isao; Itahashi, Takayuki; Ogawa, Kazuhiko; Tonoike, Kotaro; Matsumura, Tatsuro; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

1995-01-01

Japan Atomic Energy Research Institute (JAERI) has promoted the experiment research program on criticality safety since early in 1980s and two types of new critical facilities, Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) were completed on 1994 in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) of JAERI Tokai Research Establishment. STACY was designed so as to obtain critical mass data of low enriched uranium and plutonium solution which is extensively handled in LWR fuel reprocessing plant. TRACY is the critical facility where critical accident phenomenon is demonstrated with low enriched uranium nitrate solution. For criticality safety experiments with both facilities, the Fuel Treatment System is attached to them, where composition and concentration of uranium and plutonium nitrate solutions are widely varied so as to obtain experiments data covering fuel solution conditions in reprocessing plant. Design performances of both critical facilities were confirmed through mock-up tests of important components and cold function tests. Hot function test has started since January of 1995 and some of the results on STACY are to be reported. (author)

Boron Neutron Capture Therapy in the Treatment of Recurrent Laryngeal Cancer

Energy Technology Data Exchange (ETDEWEB)

Haapaniemi, Aaro, E-mail: aaro.haapaniemi@hus.fi [Department of Otorhinolaryngology–Head and Neck Surgery, Helsinki University Hospital and University of Helsinki, Helsinki (Finland); Kankaanranta, Leena [Department of Oncology, Helsinki University Hospital and University of Helsinki, Helsinki (Finland); Saat, Riste [Department of Radiology, Helsinki University Hospital and University of Helsinki, Helsinki (Finland); Koivunoro, Hanna; Saarilahti, Kauko [Department of Oncology, Helsinki University Hospital and University of Helsinki, Helsinki (Finland); Mäkitie, Antti; Atula, Timo [Department of Otorhinolaryngology–Head and Neck Surgery, Helsinki University Hospital and University of Helsinki, Helsinki (Finland); Joensuu, Heikki [Department of Oncology, Helsinki University Hospital and University of Helsinki, Helsinki (Finland)

2016-05-01

Purpose: To investigate the safety and efficacy of boron neutron capture therapy (BNCT) as a larynx-preserving treatment option for patients with recurrent laryngeal cancer. Methods and Materials: Six patients with locally recurrent squamous cell laryngeal carcinoma and 3 patients with persistent laryngeal cancer after prior treatment were treated with BNCT at the FiR1 facility (Espoo, Finland) in 2006 to 2012. The patients had received prior radiation therapy with or without concomitant chemotherapy to a cumulative median dose of 66 Gy. The median tumor diameter was 2.9 cm (range, 1.4-10.9 cm) before BNCT. Boron neutron capture therapy was offered on a compassionate basis to patients who either refused laryngectomy (n=7) or had an inoperable tumor (n=2). Boronophenylalanine-fructose (400 mg/kg) was used as the boron carrier and was infused over 2 hours intravenously before neutron irradiation. Results: Six patients received BNCT once and 3 twice. The estimated average gross tumor volume dose ranged from 22 to 38 Gy (W) (mean; 29 Gy [W]). Six of the 8 evaluable patients responded to BNCT; 2 achieved complete and 4 partial response. One patient died early and was not evaluable for response. Most common side effects were stomatitis, fatigue, and oral pain. No life-threatening or grade 4 toxicity was observed. The median time to progression within the target volume was 6.6 months, and the median overall survival time 13.3 months after BNCT. One patient with complete response is alive and disease-free with a functioning larynx 60 months after BNCT. Conclusions: Boron neutron capture therapy given after prior external beam radiation therapy is well tolerated. Most patients responded to BNCT, but long-term survival with larynx preservation was infrequent owing to cancer progression. Selected patients with recurrent laryngeal cancer may benefit from BNCT.

The ion source development for neutral injection heating at JAERI

International Nuclear Information System (INIS)

Shirakata, H.; Itoh, T.; Kondoh, U.; Matsuda, S.; Ohara, Y.; Ohga, T.; Shibata, T.; Sugawara, T.; Tanaka, S.

1976-01-01

The neutral beam research and development effort at JAERI has been mainly concentrated on design, construction and testing of ion sources needed for present and planned heating experiments. Fundamental characteristics of the ion sources developed are described

Design of a lattice for JAERI storage ring (JSR)

International Nuclear Information System (INIS)

Harada, Shunji; Yokomizo, Hideaki; Yanagida, Kenichi

1990-08-01

The new 8GeV synchrotron radiation facility (SPring-8) is planned to be constructed in Japan, and our institute (JAERI) are involved in this project with RIKEN. A compact electron storage ring JSR has been constructed in JAERI in order to study various kind of accelerator technologies, to test some devices such as the insertion devices and the beam monitors, and to train young researchers. The ring size is limited by the available space of a linac building, so that the circumference of JSR becomes 20.546 m. However, even in this small ring, one straight section with the length of ∼1.5 m, where the dispersion is free, is provided for the insertion device study. JSR takes Chasman-Green lattice with a superperiodicity of three. JSR is possible not only to suppress the dispersion but also to leave it on the long straight section. An electron beam from a linac is accepted into JSR in any operating modes. (author)

R and D thermochemical I-S process at JAERI

International Nuclear Information System (INIS)

Onuki, K.; Kubo, S.; Nakajima, H.; Higashi, S.; Kasahara, S.; Ishiyama, S.; Okuda, H.

2004-01-01

The Japan Atomic Energy Research Institute (JAERI) has conducted a study on the thermochemical water-splitting process of the iodine-sulfur family (IS process). In the IS process, water will react with iodine and sulfur dioxide to produce hydrogen iodide and sulfuric acid, which are then decomposed thermally to produce hydrogen and oxygen. High temperature nuclear heat, mainly supplied by a High Temperature Gas-cooled Reactor (HTGR), is used to drive the endothermic decomposition of sulfuric acid. JAERI has demonstrated the feasibility of the water-splitting hydrogen production process by carrying out laboratory-scale experiments in which combined operation of fundamental reactions and separations using the IS process was performed continuously. At present, the hydrogen production test is continuing, using a scaled-up glass apparatus. Corrosion-resistant materials for constructing a large-scale plant and process improvements by introducing advanced separation techniques, such as membrane separation, are under study. Future R and D items are discussed based on the present activities. (author)

Summaries of research and development activities by using JAERI computer system in FY2003. April 1, 2003 - March 31, 2004

International Nuclear Information System (INIS)

2005-03-01

Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Research Institute (JAERI) installed large computer system included super-computers in order to support research and development activities in JAERI. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and big user's research and development activities by using the computer system in FY2003 (April 1, 2003 - March 31, 2004). (author)

Extended abstracts of the 12th JAERI workshop on high-Tc superconductors

Energy Technology Data Exchange (ETDEWEB)

Hojou, Kiichi; Okayasu, Satoru; Sasase, Masato [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ishida, Takekazu [Osaka Prefectual Univ., Sakai (JP)] (eds.)

2001-03-01

This workshop was held on December 7-8, 2000 at JAERI (Tokai). The research group at JAERI shares a responsibility for material modification of high-Tc superconductors by irradiation in 'the multi-core project II of the high temperature superconducting material research' organized by STA (Science and Technology Agency) of Japan. This report contains the extended abstracts of workshop presentations covering basic theories, various experimental results and material improvement studies of the superconductivity by high energy ion irradiation. The twelve presentations of the workshop were devoted to a mini symposium where the direct observations of vortices were discussed in view of the various sophisticated techniques. (author)

JAERI 200 kV electron gun with an NEA-GaAs photocathode

International Nuclear Information System (INIS)

Nishitani, Tomohiro; Minehara, Eisuke J.; Hajima, Ryoichi; Nagai, Ryoji; Sawamura, Masaru; Nishimori, Nobuyuki; Kikuzawa, Nobuhiro; Yamauchi, Toshihiko

2004-01-01

The photocathode DC-gun with high average current, low beam emittance and long operational lifetime is considered to be indispensable for ERL-FEL. We have started the development program of a 200 keV electron gun with the NEA-GaAs photocathode for the first time in JAERI. In order to long an NEA surface lifetime, the JAERI 200 kV electron gun system consists of a 200 kV DC-gun chamber on extreme high vacuum condition and an NEA activation chamber with load-lock system. We report the goal of photocathode DC-gun R and D and the schedule of a developmental program. (author)

Extended abstracts of the 12th JAERI workshop on high-Tc superconductors

International Nuclear Information System (INIS)

Hojou, Kiichi; Okayasu, Satoru; Sasase, Masato

2001-03-01

This workshop was held on December 7-8, 2000 at JAERI (Tokai). The research group at JAERI shares a responsibility for material modification of high-Tc superconductors by irradiation in 'the multi-core project II of the high temperature superconducting material research' organized by STA (Science and Technology Agency) of Japan. This report contains the extended abstracts of workshop presentations covering basic theories, various experimental results and material improvement studies of the superconductivity by high energy ion irradiation. The twelve presentations of the workshop were devoted to a mini symposium where the direct observations of vortices were discussed in view of the various sophisticated techniques. (author)

Neutron therapy coupling brachytherapy and boron neutron capture therapy (BNCT) techniques

International Nuclear Information System (INIS)

Chaves, Iara Ferreira.

1994-12-01

In the present dissertation, neutron radiation techniques applied into organs of the human body are investigated as oncologic radiation therapy. The proposal treatment consists on connecting two distinct techniques: Boron Neutron Capture Therapy (BNCT) and irradiation by discrete sources of neutrons, through the brachytherapy conception. Biological and radio-dosimetrical aspects of the two techniques are considered. Nuclear aspects are discussed, presenting the nuclear reactions occurred in tumoral region, and describing the forms of evaluating the dose curves. Methods for estimating radiation transmission are reviewed through the solution of the neutron transport equation, Monte Carlo methodology, and simplified analytical calculation based on diffusion equation and numerical integration. The last is computational developed and presented as a quickly way to neutron transport evaluation in homogeneous medium. The computational evaluation of the doses for distinct hypothetical situations is presented, applying the coupled techniques BNTC and brachytherapy as an possible oncologic treatment. (author). 78 refs., 61 figs., 21 tabs

Recent progress in application of JAERI alanine/ESR dosimetry system

International Nuclear Information System (INIS)

Kojima, T.

1995-01-01

Feasibility studies of application of JAERI alanine/ESR dosimetry system were performed on radiotherapy level dosimetry, low dose-rate dosimetry for residual life estimation of cable insulators used in nuclear power facilities, and dose monitoring for electron processing. (author)

Transactinide nuclear chemistry at JAERI

International Nuclear Information System (INIS)

Nagame, Y.; Haba, H.; Tsukada, K.

2002-01-01

Nuclear chemistry study of trans actinide elements in Japan is currently being in progress at JAERI (Japan Atomic Energy Research Institute). We have developed new experimental apparatuses: a beam-line safety system for the usage of the gas-jet coupled radioactive 248 Cm target chamber, a rotating wheel catcher apparatus for the measurement of α and spontaneous fission decay of the transactinides, MANON (Measurement system for Alpha particles and spontaneous fission events ON line), and an automated rapid chemical separation apparatus based on the high performance liquid chromatography, AIDA (Automated Ion exchange separation system coupled with the Detection apparatus for Alpha spectroscopy). The transactinide nuclei, 261 Rf and 262 Db, have been successfully produced via the reactions of 248 Cm( 18 O,5n) and 248 Cm( 19 F,5n), respectively, and the excitation functions for each reaction have been measured to evaluate the optimum irradiation condition for the production of these nuclei. The maximum cross sections in each reaction were 13 nb at the 18 O beam energy of 94-MeV and 1.5 Nb at the 103-MeV 19 F beam energy. On-line ion exchange experiments of Rf together with the lighter homologues Zr and Hf in the HCl, HNO 3 and HF solutions with AIDA have been carried out, and the results clearly show that the behavior of Rf is typical of the group-4 element. Relativistic molecular orbital calculations of the chloride and nitrate complexes of tetravalent Rf are also being performed to gain an understanding of the complex chemistry. Prospects and some recent experimental results for the nuclear chemistry study of the transactinide elements at JAERI are discussed. (author)

Summaries of research and development activities by using JAERI computer system in FY2004 (April 1, 2004 - March 31, 2005)

International Nuclear Information System (INIS)

2005-08-01

Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Research Institute (JAERI) installed large computer systems including super-computers in order to support research and development activities in JAERI. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and the big users' research and development activities by using the computer system in FY2004 (April 1, 2004 - March 31, 2005). (author)

Proceedings of the first international symposium on neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Fairchild, R.G.; Brownell, G.L. (eds.)

1982-01-01

This meeting was arranged jointly by MIT and BNL in order to illuminate progress in the synthesis and targeting of boron compounds and to evaluate and document progress in radiobiological and dosimetric aspects of neutron capture therapy. It is hoped that this meeting will facilitate transfer of information between groups working in these fields, and encourage synergistic collaboration.

Proceedings of the first international symposium on neutron capture therapy

International Nuclear Information System (INIS)

Fairchild, R.G.; Brownell, G.L.

1982-01-01

This meeting was arranged jointly by MIT and BNL in order to illuminate progress in the synthesis and targeting of boron compounds and to evaluate and document progress in radiobiological and dosimetric aspects of neutron capture therapy. It is hoped that this meeting will facilitate transfer of information between groups working in these fields, and encourage synergistic collaboration

Recombination methods for boron neutron capture therapy dosimetry

International Nuclear Information System (INIS)

Golnik, N.; Tulik, P.; Zielczynski, M.

2003-01-01

The radiation effects of boron neutron capture therapy (BNCT) are associated with four-dose-compartment radiation field - boron dose (from 10 B(n,α) 7 Li) reaction), proton dose from 14 N(n,p) 14 C reaction, neutron dose (mainly fast and epithermal neutrons) and gamma-ray dose (external and from capture reaction 1 H(n,γ) 2 D). Because of this the relation between the absorbed dose and the biological effects is very complex and all the above mentioned absorbed dose components should be determined. From this point of view, the recombination chambers can be very useful instruments for characterization of the BNCT beams. They can be used for determination of gamma and high-LET dose components for the characterization of radiation quality of mixed radiation fields by recombination microdosimetric method (RMM). In present work, a graphite high-pressure recombination chamber filled with nitrogen, 10 BF 3 and tissue equivalent gas was used for studies on application of RMM for BNCT dosimetry. The use of these gases or their mixtures opens a possibility to design a recombination chamber for determination of the dose fractions due to gamma radiation, fast neutrons, neutron capture on nitrogen and high LET particles from (n, 10 B) reaction in simulated tissue with different content of 10 B. (author)

Waste management for JAERI fusion reactors

International Nuclear Information System (INIS)

Tobita, K.; Nishio, S.; Konishi, S.; Jitsukawa, S.

2004-01-01

In the fusion reactor design study at Japan Atomic Energy Institute (JAERI), several waste management strategies were assessed. The assessed strategies are: (1) reinforced neutron shield to clear the massive ex-shielding components from regulatory control; (2) low aspect ratio tokamak to reduce the total waste; (3) reuse of liquid metal breeding material and neutron shield. Combining these strategies, the weight of disposal waste from a low aspect ratio reactor VECTOR is expected to be comparable with the metal radwaste from a light water reactor (∼4000 t)

SBNCT plan: A 3-dimensional treatment planning system for boron neutron capture therapy

International Nuclear Information System (INIS)

Reinstein, L.E.; Ramsay, E.B.; Gajewski, J.; Ramamoorthy, S.; Meek, A.G.

1993-01-01

The need for accurate and comprehensive 3-dimensional treatment planning for boron neutron capture therapy (BNCT) has been debated for the past several years. Although many argue against the need for elaborate and expensive treatment planning programs which mimic conventional radiotherapy planning systems, it is clear that in order to realize significant gains over conventional fractionated radiation therapy, patients must be treated to the edge of normal tissue tolerance. Just how close to this edge is dictated by the uncertainties in dosimetry. Hence the focus of BNCT planning is the determination of dose distribution throughout normal tissue volumes. Although precise geometric manipulation of the epithermal neutron beam is not achievable, the following variables play an important role in BNCT optimization: patient orientation, dose fractionation, number of fields, megawatt-minutes per fraction, use of surface bolus, and use of collimation. Other variables which are not as easily adjustable and would not, therefore, be part of treatment planning optimization, include external patient contour, internal patient heterogeneities, boron compound distributions, and RBE's. The boron neutron capture therapy planning system developed at SUNY Stony Brook (SBNCT-Plan) was designed as an interactive graphic tool to assist the radiation oncologist in generating the optimum plan for a neutron capture treatment

Cable systems for experimental facilities in JAERI TANDEM ACCELERATOR BUILDING

International Nuclear Information System (INIS)

Tukihashi, Yoshihiro; Yoshida, Tadashi; Takekoshi, Eiko

1979-03-01

Measuring cable systems for experimental facilities in JAERI TANDEM ACCELERATOR BUILDING were completed recently. Measures are taken to prevent penetration of noises into the measuring systems. The cable systems are described in detail, including power supplies and grounding for the measuring systems. (author)

Proceedings of the 1st JAERI symposium on HTGR technologies

International Nuclear Information System (INIS)

1990-07-01

This report was edited as the Proceedings of the 1st JAERI Symposium on HTGR Technologies, - Design, Licensing Requirements and Supporting Technologies -, collecting the 21 papers presented in the Symposium. The 19 of the presented papers are indexed individually. (J.P.N.)

Workshop of Advanced Science Research Center, JAERI. Nuclear physics and nuclear chemistry of superheavy elements

International Nuclear Information System (INIS)

Nishio, Katsuhisa; Nishinaka, Ichiro; Ikezoe, Hiroshi; Nagame, Yuichiro

2004-03-01

A liquid drop model predicts that the fission barrier of a nucleus whose atomic number (Z) is larger than 106 disappears, so that such heavier nuclei as Z > 106 cannot exist. The shell effect, however, drastically changes structure of the fission barrier and stabilizes nucleus against fission, predicting the presence of super heavy element (SHE, Z=114-126) with measurable half-life. In the SHE region, a wave function of outermost electron of an atom, which controls chemical properties of an elements, is disturbed or changed by relativistic effects compared to the one from the non-relativistic model. This suggests that the SHEs have different chemical properties from those of lighter elements belonging to the same family. The chemistry of SHEs requires event by event analysis to reveal their chemical properties, thus is called 'atom-at-a-time chemistry'. Japan Atomic Energy Research Institute (JAERI) has been investigating fusion mechanism between heavy nuclei to find out favorable reactions to produce SHE by using JAERI-tandem and booster accelerator. In the JAERI-tandem facility, isotopes of Rf and Db are produced by using actinide targets such as 248 Cm in order to investigate their chemical properties. The present workshop was held in Advanced Science Research Center of JAERI at February 27-28 (2003) in order to discuss current status and future plans for the heavy element research. The workshop also included topics of the radioactive nuclear beam project forwarded by the JAERI-KEK cooperation and the nuclear transmutation facility of J-PARC. Also included is the nuclear fission process as a decay characteristic of heavy elements. There were sixty participants in the workshop including graduate and undergraduate eleven students. We had guests from Germany and Hungary. Through the workshop, we had a common knowledge that researches on SHE in Japan should fill an important role in the world. (author)

Generation of Coherent Synchrotron Radiation from JAERI-ERL

CERN Document Server

Hajima, R; Kikuzawa, N; Minehara, E J; Nagai, R; Nishitani, T; Sawamura, M

2005-01-01

An electron beam with high-average current and short bunch length can be accelerated by energy-recovery linac. Coherent synchrotron radiation (CSR) from such an electron beam will be a useful light source around millimeter wavelength. We report results from a preliminary measurement of CSR emitted from a bending magnet of JAERI-ERL. Possible enhancement of CSR power by FEL micro-bunching is also discussed.

Thiourea derivatives, methods of their preparation and their use in neutron capture therapy of malignant melanoma

Energy Technology Data Exchange (ETDEWEB)

Gabel, D.

1991-06-04

The present invention pertains to boron containing thiouracil derivatives, their method of preparations, and their use in the therapy of malignant melanoma using boron neutron capture therapy. No Drawings

Cost benefit effect of application of radiation in JAERI

International Nuclear Information System (INIS)

Kazuaki Yanagisawa

2009-01-01

It is important for us to show accountability and transparency of nuclear funds invested to Japan Atomic Energy Research Institute (JAERI, now JAEA). We have not only to simply present the R and D outputs to tax payers by the bibliometric methods as measurable as possible but also to carry out a cost benefit analysis to show quantitatively the effect of economic representation which enables to make efficient allotment of resources. The task is heavy but unavoidable. In the present work, a cost benefit effect (CBE) of application of radiation known as one of big R and D project conducted in JAERI-Takasaki Branch is focused on. After defining CBE as Market Creation Effect (MCE) / Total amounts of investment, one tried to reveal the long-term CBE as long as 44 years. It is found that 31 research items, such as radial tires, cross-linking of wires, sterilization, and sterile of melon flies were succeeded to create markets in industrial and agricultural fields. Estimated MCE of those was totaled to 1,125 million dollars (M$). On the other hand, investment was 396 M$ for personnel (4,092 man/year) and 509 M$ for research costs. It totaled as 905 M$. Therefore, CBE for application of radiation in Takasaki Branch shall be 1,125/905=1.2. The mission dictated by the Long-Range Research Plan for Nuclear settled by the Atomic Energy Commission involves a lot of R and D tasks including partly the technical difficulties as well as partly the deep uncertainties for future prospects. JAERI is a national research institute and this figure may be regarded as reasonably acceptable because of many high risk and complex tasks were conducted successfully resulting in the creation of 31 new markets. It contributed to the increase of GDP. (Author)

Overview of HTGR heat utilization system development at JAERI

International Nuclear Information System (INIS)

Miyamoto, Y.; Shiozawa, S.; Ogawa, M.; Akino, N.; Shimizu, S.; Hada, K.; Inagaki, Y.; Onuki, K.; Takeda, T.; Nishihara, T.

1998-01-01

The Japan Atomic Energy Research Institute (JAERI) has conducted research and development of nuclear heat utilization systems of a High Temperature Gas cooled Reactor (HTGR), which are capable to meet a large amount of energy demand without significant CO 2 emission to relax the global warming issue. The High Temperature engineering Test Reactor (HTTR) with thermal output of 30 MW and outlet coolant temperature of 950 deg C, the first HTGR in Japan, is under construction on the JAERI site, and its first criticality is scheduled for mid-1998. After the reactor performance and safety demonstration tests for several years, a hydrogen production system will be connected to the HTTR. A demonstration program on hydrogen production started in January 1997, in JAERI, as a study consigned by the Science and Technology Agency. A hydrogen production system connected to the HTTR is designed to be able to produce hydrogen by steam reforming of natural gas, using nuclear heat of 10 MW from the HTTR. The safety principle and standard are investigated for the HTTR hydrogen production system. In order to confirm safety, controllability and performance of key components in the HTTR hydrogen production system, an out-of-pile test facility on the scale of approximately 1/30 of the HTTR hydrogen production system is installed. It is equipped with an electric heater as a heat source instead of the HTTR. The out-of-pile test will be performed for four years after 2001. The HTTR hydrogen production system will be demonstratively operated after 2005 at its earliest plan. Other basic studies on the hydrogen production system using thermochemical water splitting, an iodine sulphur (IS) process, and technology of distant heat transport with microencapsulated phase change material have been carried out for more effective and various uses of nuclear heat. (author)

Boron neutron capture therapy for malignant melanoma: An experimental approach

Energy Technology Data Exchange (ETDEWEB)

Larsson, B.S.; Larsson, B.; Roberto, A. (Uppsala Univ. (Sweden))

1989-07-01

Previous studies have shown that some thioamides, e.g., thiouracil, are incorporated as false precursors into melanin during its synthesis. If boronated analogs of the thioamides share this property, the melanin of melanotic melanomas offers a possibility for specific tumoural uptake and retention of boron as a basis for neutron capture therapy. We report on the synthesis of boronated 1H-1,2,4-triazole-3-thiol (B-TZT), boronated 5-carboxy-2-thiouracil (B-CTU), and boronated 5-diethylaminomethyl-2-thiouracil (B-DEAMTU) and the localization of these substances in melanotic melanomas transplanted to mice. The distribution in the mice was studied by boron neutron capture radiography. B-TZT and B-CTU showed the highest tumour:normal tissue concentration ratios, with tumour:liver ratios of about 4 and tumour:muscle ratios of about 14; B-DEAMTU showed corresponding ratios of 1.4 and 5, respectively. The absolute concentration of boron in the tumours, however, was more than three times higher in the mice injected with B-TZT, compared with B-CTU. The results suggest that B-TZT may be the most promising compound of the three tested with regard to possible therapy of melanotic melanomas.

Collaborative analysis for certification of zirconium and zirconium base alloy reference materials JAERI-Z11 to Z16

International Nuclear Information System (INIS)

1985-03-01

The second Sub-Committee on Zircaloy Analysis was organized in April 1978, under the Committee on Analytical Chemistry on Nuclear Fuels and Reactor Materials, JAERI, for the renewal of zirconium and zirconium base alloy certified reference materials (CRMs). The Sub-Committee carried out collaborative analysis among 13 participating laboratories for the certification of the CRMs, JAERI-Z11 to Z18, after development, improvement and evaluation of analytical methods during the period of May 1978 to June 1982. As the result of the collaborative analysis, the certified value was given for 18 elements (Sn, Fe, Ni, Cr, B, Cd, U, Cu, Co, Mn, Pb, Al, Ti, Si, Mo, W, Hf, C) in the CRMs. The first part of this report includes general discussion, the second part principles of certification, the third part development and verification of analytical methods, and the fourth part evaluation of analytical results on 17 elements. Preparation of Z11 to Z18, and certification for carbon in JAERI-Z17 and Z18 were reported separately in JAERI-M 83-241 and M 83-035, respectively. (author)

Iodine neutron capture therapy

Science.gov (United States)

Ahmed, Kazi Fariduddin

A new technique, Iodine Neutron Capture Therapy (INCT) is proposed to treat hyperthyroidism in people. Present thyroid therapies, surgical removal and 131I treatment, result in hypothyroidism and, for 131I, involve protracted treatment times and excessive whole-body radiation doses. The new technique involves using a low energy neutron beam to convert a fraction of the natural iodine stored in the thyroid to radioactive 128I, which has a 24-minute half-life and decays by emitting 2.12-MeV beta particles. The beta particles are absorbed in and damage some thyroid tissue cells and consequently reduce the production and release of thyroid hormones to the blood stream. Treatment times and whole-body radiation doses are thus reduced substantially. This dissertation addresses the first of the several steps needed to obtain medical profession acceptance and regulatory approval to implement this therapy. As with other such programs, initial feasibility is established by performing experiments on suitable small mammals. Laboratory rats were used and their thyroids were exposed to the beta particles coming from small encapsulated amounts of 128I. Masses of 89.0 mg reagent-grade elemental iodine crystals have been activated in the ISU AGN-201 reactor to provide 0.033 mBq of 128I. This activity delivers 0.2 Gy to the thyroid gland of 300-g male rats having fresh thyroid tissue masses of ˜20 mg. Larger iodine masses are used to provide greater doses. The activated iodine is encapsulated to form a thin (0.16 cm 2/mg) patch that is then applied directly to the surgically exposed thyroid of an anesthetized rat. Direct neutron irradiation of a rat's thyroid was not possible due to its small size. Direct in-vivo exposure of the thyroid of the rat to the emitted radiation from 128I is allowed to continue for 2.5 hours (6 half-lives). Pre- and post-exposure blood samples are taken to quantify thyroid hormone levels. The serum T4 concentration is measured by radioimmunoassay at

Neutron capture therapy beams at the MIT Research Reactor

International Nuclear Information System (INIS)

Choi, J.R.; Clement, S.D.; Harling, O.K.; Zamenhof, R.G.

1990-01-01

Several neutron beams that could be used for neutron capture therapy at MITR-II are dosimetrically characterized and their suitability for the treatment of glioblastoma multiforme and other types of tumors are described. The types of neutron beams studied are: (1) those filtered by various thicknesses of cadmium, D2O, 6Li, and bismuth; and (2) epithermal beams achieved by filtration with aluminum, sulfur, cadmium, 6Li, and bismuth. Measured dose vs. depth data are presented in polyethylene phantom with references to what can be expected in brain. The results indicate that both types of neutron beams are useful for neutron capture therapy. The first type of neutron beams have good therapeutic advantage depths (approximately 5 cm) and excellent in-phantom ratios of therapeutic dose to background dose. Such beams would be useful for treating tumors located at relatively shallow depths in the brain. On the other hand, the second type of neutron beams have superior therapeutic advantage depths (greater than 6 cm) and good in-phantom therapeutic advantage ratios. Such beams, when used along with bilateral irradiation schemes, would be able to treat tumors at any depth in the brain. Numerical examples of what could be achieved with these beams, using RBEs, fractionated-dose delivery, unilateral, and bilateral irradiation are presented in the paper. Finally, additional plans for further neutron beam development at MITR-II are discussed

Development of EC technology in JAERI

International Nuclear Information System (INIS)

Sakamoto, Keishi; Takahashi, Koji; Kasugai, Atsushi; Hayashi, Kenichi; Ikeda, Yoshitaka; Kajiwara, Ken; Fujii, Tsuneyuki; Imai, Tsuyoshi; Kariya, Tsuyoshi; Mitsunaka, Yoshika

2003-01-01

Recent progress of electron cyclotron (EC) heating and current drive technologies in JAERI is reported. In 170 GHz gyrotron development, 0.9 MW/9.2 sec (efficiency: 43%), 0.5 MW/30 sec (46%), etc, have been demonstrated. As for 110 GHz gyrotron, 1 MW/5 sec and 1.2 MW/4.1 sec were obtained. Using four 110 GHz gyrotrons, a 3 MW power injection into JT- 60U plasma was carried out. In parallel, a launcher design and its development that includes neutron irradiation of the launcher components and a remote steering launcher are underway for ITER application. (authors)

Analyses of superradiance and spiking-mode lasing observed at JAERI-FEL

CERN Document Server

Hajima, R; Nagai, R; Minehara, E J

2001-01-01

Japan Atomic Energy Research Institute (JAERI)-FEL has achieved quasi-CW lasing with an average power of 1.7 kW, the initial goal of the R and D program. The FEL extraction efficiency obtained completely exceeds the well-known limit for non-bunched beam, which is determined by the number of undulator periods. We have conducted numerical studies to characterize lasing dynamics observed at JAERI-FEL. Cavity-length detuning curves numerically obtained show good agreement with experimental results. Lasing behavior numerically obtained exhibits chaotic spiking-mode and superradiance as the cavity-length detuning approaches zero. Broadening of lasing spectrum observed in the experiments is explained by these lasing dynamics. The extraction efficiency becomes maximal at the perfect synchronization of the cavity length, where the lasing is quasi-stationary superradiance. We also compare these results with analytical theory previously reported.

Investigation regarding the amount of disused components and the radioactive inventory at Mutsu Establishment, JAERI

International Nuclear Information System (INIS)

Hatanaka, Kazuo; Ooeda, Etsurou; Watanabe, Masaaki

2003-01-01

About 200 tons of the disused components, which were used for fuel removal, are stored in Mutsu Establishment, Japan Atomic Energy Research Institute (JAERI). In order to settle the decommissioning plan, RANDEC made an investigation regarding the amount of disused components and the radioactive inventory in Mutsu Establishment under a contract with JAERI. This report describes the estimation results of radioactive inventory and weight of radioactive wastes regarding the disused equipment such as an ion-exchange resin tank, a injection pump and equipment for fuel removal. (author)

Slow neutron capture therapy for malignant glioma (boron or lithium neutron capture therapy)

International Nuclear Information System (INIS)

Hatanaka, Hiroshi

1981-01-01

In recurrent glioblastoma, the mean survival period is approx. 6 months by the routine methods of treatment, but is extended more than 3-fold by neutron capture therapy. This method and a routine method with 60 Co or an accelerator were used for comparison in the clinical treatment of 26 patients with supratentorial malignant glioma. There were no significant differences as for prognostic factors of the group treated by this method and those of the control group; No. of cases 14 and 12, the mean age 46 and 53.5 yr, and the stage (TNM) 3.14 and 2.83, respectively. As of the end of Feb. 1980, this method showed a lifeprolonging effect 3 times that of the control, the mean survival period being 67 weeks for this method and 21 for the control. Although 100% improvement was observed in about one half of the cases by this method, the control group showed improvement of only 80% at maximum. It is also possible to treat any deep portion of the brain with thermal neutrons. As a Boron compound, mercaptoundecahydrododecarborate with a low toxicity has been put into practical use for brain tumors, and as Li, the use of 6 LiCl for lung cancer is under examination. (Chiba, N.)

Dose modification factors in boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Allen, B.J. (Australian Nuclear Science and Technology Organization (ANSTO), Menai (Australia))

1993-01-01

The effective treatment depth and therapeutic ratio in boron neutron capture therapy (BNCT) depend on a number of macroscopic dose factors such as boron concentrations in the tumor, normal tissue and blood. However, the role of various microscopic dose modification factors can be of critical importance in the evaluation of normal tissue tolerance levels. An understanding of these factors is valuable in designing BNCT experiments and the selection of appropriate boron compounds. These factors are defined in this paper and applied to the case of brain tumors with particular attention to capillary endothelial cells and oligodendrocytes. (orig.).

Novel amino-carboxy-dihydroboranes for neutron capture therapy

International Nuclear Information System (INIS)

Boehmel, T.

1985-01-01

The thesis discusses the following topics: I. Synthesis of boron compounds for the neutron capture therapy which are to meet the following requirements: 1. Low toxicity; 2. High boron content; 3. High enrichment and long retention time in the neoplastic tissue and simultaneous low concentration in blood and normal tissue; 4. Independent cytostatic effects; 5. Functional groups which allow a connection with polymers. II. Presentation of compounds with increased 10 B content. III. Examination of the distribution of boric substances in living organisms by means of a quantitative analysis of the boron content. (orig./PW) [de

Monte Carlo based dosimetry and treatment planning for neutron capture therapy of brain tumors

International Nuclear Information System (INIS)

Zamenhof, R.G.; Clement, S.D.; Harling, O.K.; Brenner, J.F.; Wazer, D.E.; Madoc-Jones, H.; Yanch, J.C.

1990-01-01

Monte Carlo based dosimetry and computer-aided treatment planning for neutron capture therapy have been developed to provide the necessary link between physical dosimetric measurements performed on the MITR-II epithermal-neutron beams and the need of the radiation oncologist to synthesize large amounts of dosimetric data into a clinically meaningful treatment plan for each individual patient. Monte Carlo simulation has been employed to characterize the spatial dose distributions within a skull/brain model irradiated by an epithermal-neutron beam designed for neutron capture therapy applications. The geometry and elemental composition employed for the mathematical skull/brain model and the neutron and photon fluence-to-dose conversion formalism are presented. A treatment planning program, NCTPLAN, developed specifically for neutron capture therapy, is described. Examples are presented illustrating both one and two-dimensional dose distributions obtainable within the brain with an experimental epithermal-neutron beam, together with beam quality and treatment plan efficacy criteria which have been formulated for neutron capture therapy. The incorporation of three-dimensional computed tomographic image data into the treatment planning procedure is illustrated. The experimental epithermal-neutron beam has a maximum usable circular diameter of 20 cm, and with 30 ppm of B-10 in tumor and 3 ppm of B-10 in blood, it produces a beam-axis advantage depth of 7.4 cm, a beam-axis advantage ratio of 1.83, a global advantage ratio of 1.70, and an advantage depth RBE-dose rate to tumor of 20.6 RBE-cGy/min (cJ/kg-min). These characteristics make this beam well suited for clinical applications, enabling an RBE-dose of 2,000 RBE-cGy/min (cJ/kg-min) to be delivered to tumor at brain midline in six fractions with a treatment time of approximately 16 minutes per fraction

Measurement of concentrations of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility

Energy Technology Data Exchange (ETDEWEB)

Endo, Akira; Kawasaki, Katsuya; Kikuchi, Masamitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Harada, Yasunori

1997-07-01

Measurement has been made to study distributions of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility. Core boring was carried out at seven positions to take samples from the concrete shield, and {gamma}-ray counting rates and {gamma}-ray spectra of these samples were measured with a NaI(Tl) detector and a Ge semiconductor detector, respectively. The following radionuclides were detected in the concrete samples: {sup 60}Co, {sup 134}Cs, {sup 152}Eu and {sup 154}Eu generated through thermal neutron capture reaction, and {sup 22}Na and {sup 54}Mn generated through nuclear reactions by bremsstrahlung and fast neutrons. The relation between the distributions of {gamma}-ray emitters, as a function of the depth of concrete, and the positions of core boring is discussed. (author)

Considerations for boron neutron capture therapy studies

International Nuclear Information System (INIS)

Faria Gaspar, P. de.

1994-01-01

Radiotherapy is indispensable as a mean to eradicate deeply or infiltrating tumor tissue that can not be removed surgically. Therefore, it is not selective and may also kill the surrounding health tissue. The principle of BNCT (Boron Neutron Capture Therapy) consist in targeting a tumor selectively with a boron-10 compound. This nuclide has a large capture cross section for thermal neutrons and the nuclear reaction and the delivered energy in locus will selective the tumor. Since its initial proposal in 1963 BNCT has made much progress, however it is not used in a routine treatment. In this work it was approached some complex procedures, as the obtention of selective boron compounds, the adequate set up of neutron beams, the biodistribution, the in vivo and in vitro studies, and also human patients treatments. This work provide fundamentals about BNCT to professional of different areas of knowledge since it comprises multidisciplinary study. It includes appendixes for the ones not related to the field for a better comprehension of the many aspects involved. It is also presented a glossary containing technical and basic aspects involved. It is also presented a glossary containing technical and basic terms referred in the work. (author). 174 refs, 1 fig, 12 apps

JAERI tandem, linac and V.D.G. annual report 1984

International Nuclear Information System (INIS)

Shikazono, Naomoto; Iizumi, Masashi; Ishii, Mitsuhiko; Kawarasaki, Yuuki; Murayama, Michio; Okashita, Hiroshi; Ozawa, Kunio; Suto, Yoichi

1985-07-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1984 to March 31, 1985. Summary reports of 53 papers, publications, personnel and a list of cooperative researches with universities are contained. (author)

JAERI tandem, linac and V.D.G. annual report 1987

International Nuclear Information System (INIS)

1988-10-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1987 to March 31, 1988. Summary reports of 49 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM, LINAC and V.D.G. annual report 1989

International Nuclear Information System (INIS)

1990-09-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1989 to March 31, 1990. Summary reports of 49 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI Tandem, LINAC and V.D.G. annual report 1986

International Nuclear Information System (INIS)

1987-08-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1986 to March 31, 1987. Summary reports of 55 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

First results of beam generation test for JAERI AVF cyclotron

International Nuclear Information System (INIS)

Tachikawa, T.; Hayashi, Y.; Ishii, K.

1992-01-01

The performance of JAERI AVF cyclotron was investigated with several kinds of ions in the wide energy range. The 90 MeV protons of 10 μA intensity was successfully extracted for the first time by the model 930 cyclotron. The feature of beam chopping system is also presented. (author)

JAERI tandem, LINAC and V.D.G. annual report 1988

International Nuclear Information System (INIS)

1989-09-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1988 to March 31, 1989. Summary reports of 45 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM, LINAC and V.D.G. annual report, 1985

International Nuclear Information System (INIS)

1986-08-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1985 to March 31, 1986. Summary reports of 52 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

Research activities at JAERI on core material behaviour under severe accident conditions

International Nuclear Information System (INIS)

Uetsuka, H.; Katanashi, S.; Ishijima, K.

1996-01-01

At the Japan Atomic Energy Research Institute (JAERI), experimental studies on physical phenomena under the condition of a severe accident have been conducted. This paper presents the progress of the experimental studies on fuel and core materials behaviour such as the thermal shock fracture of fuel cladding due to quenching, the chemical interaction of core materials at high temperatures and the examination of TMI-2 debris. The mechanical behaviour of fuel rod with heavily embrittled cladding tube due to the thermal shock during delayed reflooding have been investigated at the Nuclear Safety Research Reactor (NSSR) of JAERI. A test fuel rod was heated in steam atmosphere by both electric and nuclear heating using the NSSR, then the rod was quenched by reflooding at the test section. Melting of core component materials having relatively low melting points and their eutectic reaction with other materials significantly influence on the degradation and melt down of fuel bundles during severe accidents. Therefore basic information on the reaction of core materials is necessary to understand and analyze the progress of core melting and relocation. Chemical interactions have been widely investigated at high temperatures for various binary systems of core component materials including absorber materials such as Zircaloy/Inconel, Zircaloy/stainless steel, Zircaloy/(Ag-In-Cd), stainless steel B 4 C and Zircaloy/B 4 C. It was found that the reaction generally obeyed a parabolic rate law and the reaction rate was determined for each reaction system. Many debris samples obtained from the degraded core of TMI-2 were transported to JAERI for numerous examinations and analyses. The microstructural examination revealed that the most part of debris was ceramic and it was not homogeneous in a microscopic sense. The thermal diffusivity data was also obtained for the temperature range up to about 1800K. The data from the large scale integral experiments were also obtained through the

Design studies of Tokamak power reactor in JAERI

International Nuclear Information System (INIS)

Tone, T.; Nishikawa, M.; Tanaka, Y.

1985-01-01

Recent design studies of tokamak power reactor and related activities conducted in JAERI are presented. A design study of the SPTR (Swimming-Pool Type Reactor) concept was carried out in FY81 and FY82. The reactor design studies in the last two years focus on nuclear components, heat transport and energy conversion systems. In parallel of design studies, tokamak systems analysis code is under development to evaluate reactor performances, cost and net energy balance

Neutron capture therapy of ocular melanoma: dosimetry and microdosimetry approaches

International Nuclear Information System (INIS)

Pignol, J.P.; Methlin, G.; Abbe, J.C.; Lefebvre, O.; Sahel, J.

1994-01-01

Neutron capture therapy (NCT) aims at destroying cancerous cells with the α and 7 Li particles produced by the neutron capture reaction on 10 B. This note reports on the study of the boron distribution in tissues on an animal model (nude mice) xenografted with a human ocular melanoma after an i.p.injection of 2g/kg of 10 B-BPA and in cells cultured in the presence of 530 μmol/l of 10 B-BPA. A concentration of 64 ppm of 10 B in the active part of the tumour with a ratio of concentrations versus the skin of 3.7 are observed. Investigations on cells reveal the presence of boron in the cytoplasm. The biological, dosimetric and microdosimetric consequences of these findings are discussed. (authors). 15 refs., 2 tabs., 2 figs

Physico-technical progress in neutron-capture therapy method

International Nuclear Information System (INIS)

Kanda, Keiji; Furubayashi, Toru; Aoki, Kazuhiko

1985-01-01

This paper describes mainly development studies on the determination method of in vivo 10 B for the purpose of employment for neutron capture therapy for malignant melanoma and other tumors. To darify the efficacy of the neutron capture therapy, it is necessary to determine 10 B concentration in the diseased part. This study aimed at in vivo 10 B concention determination in living sample to the level of ppm order with 10 % of analytical error within 1 hour, and these determination conditions were satified by prompt γ-ray (478 keV) determination of 10 B (n, αγ) 7 Li reaction. This method required no sample pretreatment. Further, data normalization by γ-ray of H(n, γ)D reaction permitted no disturbance by sample shape or size. Lower limit of detection of the proposed method was estimated in terms of measuring time and statistical error by the equations of 10 B concentration and error analysis derived by the authors. As for the effect of prompt γ-rays of 23 Na(n, γ) 24 Na and 6 Li(n, γ) 7 Li reactions, it was clarified that the former showed no disturbance but some correction was necessary in case of less than 0.1 g of smaple size owing to the latter reaction. In vivo sample determination showed the proposed method was practical. In this paper some results of phantom experiment for in vivo non-destructive 10 B measurement and related simulation calculation, and examination of effect of (γ, n) reaction in heavy water of biomedical irradiation equipment on radiation quality were also described. (Takagi, S.)

Selection of JAERI'S HTGR-GT concept

International Nuclear Information System (INIS)

Muto, Y.; Ishiyama, S.; Shiozawa, S.

2001-01-01

In JAERI, a feasibility study of HTGR-GT has been conducted as an assigned work from STA in Japan since January 1996. So far, the conceptual or preliminary designs of 600, 400 and 300 MW(t) power plants have been completed. The block type core and pebble-bed core have been selected in 600 MW(t) and 400/300 MW(t), respectively. The gas-turbine system adopts a horizontal single shaft rotor and then the power conversion vessel is separated into a turbine vessel and a heat exchanger vessel. In this paper, the issues related to the selection of these concepts are technically discussed. (author)

Experience of boron neutron capture therapy in Japan

International Nuclear Information System (INIS)

Kanda, K.

2004-01-01

Four research reactors are currently licensed for medical application in Japan. As of July 1995, approximately 210 clinical irradiations using these research reactors have been done for brain and skin tumors as shown. The number of chief medical doctors certified by the Government is eleven so far. Among them, eight doctors have already treated tumor patients using the Kyoto University Reactor (KUR, 5MW). Recently in USA clinical trials have been restarted using epithermal neutrons at MIT and BNL. In this paper, the experience of clinical trials of boron neutron capture therapy (BNCT) which have been performed in Japan, mainly physics studies, are reviewed, and current studies are also introduced

Antitumor potential induction and free radicals production in melanoma cells by Boron Neutron Capture Therapy

Energy Technology Data Exchange (ETDEWEB)

Faiao-Flores, F. [Biochemical and Biophysical Laboratory, Butantan Institute, 1500 Vital Brasil Avenue, Sao Paulo (Brazil)] [Faculty of Medicine, University of Sao Paulo, 455 Doutor Arnaldo Avenue, Sao Paulo (Brazil); Coelho, P.R.P.; Muniz, R.O.R.; Souza, G.S. [Institute for Nuclear and Energy Research, 2242 Lineu Prestes Avenue, Sao Paulo (Brazil); Arruda-Neto, J. [Physics Institute, University of Sao Paulo, 187 Matao Street, Sao Paulo (Brazil)] [FESP, Sao Paulo Engineering School, 5520 Nove de Julho Avenue, Sao Paulo (Brazil); Maria, Durvanei A., E-mail: durvaneiaugusto@yahoo.com.br [Biochemical and Biophysical Laboratory, Butantan Institute, 1500 Vital Brasil Avenue, Sao Paulo (Brazil)

2011-12-15

Antiproliferative and oxidative damage effects occurring in Boron Neutron Capture Therapy (BNCT) in normal fibroblasts and melanoma cell lines were analyzed. Melanoma cells and normal fibroblasts were treated with different concentrations of Boronophenylalanine and irradiated with thermal neutron flux. The cellular viability and the oxidative stress were determined. BNCT induced free radicals production and proliferative potential inhibition in melanoma cells. Therefore, this therapeutic technique could be considered efficient to inhibit growth of melanoma with minimal effects on normal tissues. - Highlights: Black-Right-Pointing-Pointer Boron Neutron Capture Therapy (BNCT) induces melanoma cell death. Black-Right-Pointing-Pointer BNCT stimulates free radicals production and proliferative inhibition in melanoma cells. Black-Right-Pointing-Pointer It produces tumor membrane degeneration and destruction with apoptotic bodies formation. Black-Right-Pointing-Pointer This therapy damages tumor cells selectively, with minimum effects on normal adjacent tissue.

Scaling of the optical parameters for the JAERI tandem accelerator

International Nuclear Information System (INIS)

Hanashima, S.; Minehara, E.

1986-01-01

A scaling rule of the beam optical parameters was adopted for computer-aided beam transport in the JAERI tandem accelerator. Tests have shown that the computer program can transport a specified beam in a short time using a reference parameter set. Problems of ion source control and accuracy of the optical devices are also discussed

Boron neutron capture therapy: Brain Tumor Treatment Evaluation Program

International Nuclear Information System (INIS)

Griebenow, M.L.; Dorn, R.V. III; Gavin, P.R.; Spickard, J.H.

1988-01-01

The United States (US) Department of Energy (DOE) recently initiated a focused, multidisciplined program to evaluate Boron Neutron Capture Therapy (BNCT) for the treatment of brain tumors. The program, centered at the DOE/endash/Idaho National Engineering Laboratory (INEL), will develop the analytical, diagnostic and treatment tools, and the database required for BNCT technical assessment. The integrated technology will be evaluated in a spontaneously-occurring canine brain-tumor model. Successful animal studies are expected to lead to human clinical trials within four to five years. 2 refs., 3 figs

Research needs for neutron capture therapy

International Nuclear Information System (INIS)

1995-01-01

Key issues and questions addressed by the workshop related to optimization of Boron Neutron Capture Therapy (BNCT), in general, and to the possibility of success of the present BNCT trials at Brookhaven National Laboratory (BNL) and Massachusetts Institute of Technology (MIT), in particular. Both trials use nuclear fission reactors as neutron sources for BNCT of glioblastoma multiforme (BNL) and of deep seated melanoma (MIT). Presentations and discussions focussed on optimal boron-labeled compounds, mainly for brain tumors such as glioblastoma multiforme, and the best mode of compound delivery to the tumor. Also, optimizing neutron irradiation with dose delivery to the tumor cells and the issues of dosimetry of BNCT especially in the brain were discussed. Planning of treatment and of follow-up of patients, coordination of BNCT at various treatment sites, and the potential of delivering BNCT to various types of cancer with an appropriately tailored protocol were additional issues. The need for multicentric interdisciplinary cooperation among the different medical specialties was highlighted

JAERI tandem annual report 2002. April 1, 2002 - March 31, 2003

International Nuclear Information System (INIS)

Takeuchi, Suehiro; Oshima, Masumi; Ishii, Tetsuro; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

2003-11-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2002 to March 31, 2003. Summary reports of 54 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

JAERI TANDEM annual report 2000. April 1, 2000 - March 31, 2001

Energy Technology Data Exchange (ETDEWEB)

Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Nagame, Yuichiro; Sataka, Masao; Iwamoto, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (eds.)

2001-11-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2000 to March 31, 2001. Summary reports of 46 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

JAERI tandem annual report 2001. April 1, 2001 - March 31, 2002

Energy Technology Data Exchange (ETDEWEB)

Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Nagame, Yuichiro; Sataka, Masao; Iwamoto, Akira (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-11-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2001 to March 31, 2002. Summary reports of 48 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

JAERI tandem annual report 1999. April 1, 1999 - March 31, 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-11-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1999 to March 31, 2000. Summary reports of 49 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

Development program on HTTR heat application systems at JAERI

International Nuclear Information System (INIS)

Ogawa, M.; Inagaki, Y.; Nishihara, T.; Shimizu, S.; Shiozawa, S.; Miyamoto, Y.

2000-01-01

The High Temperature Engineering Test Reactor (HTTR), which is a Japanese High Temperature Gas-cooled Reactor (HTGR) with 30 MW thermal output at 950 deg. C of the coolant outlet temperature, was constructed at Oarai Research Establishment of Japan Atomic Energy Research Institute (JAERI). The HTTR has attained the first criticality on November 1998. In JAERI, a hydrogen production system was selected as a heat utilization system of the HTTR. The development program on the HTTR hydrogen production system consists of two parts: one is to establish technologies connecting the hydrogen production system with the HTTR, the other is to establish technologies producing hydrogen from water by using nuclear heat. Finally, hydrogen can be produced from water by using nuclear heat supplied by the HTTR. In the hydrogen production system connected to the HTTR at first, JAERI selected a steam reforming process because its technology had matured. The HTTR hydrogen production system adopting the steam reforming process is being designed to produce hydrogen of about 3800 Nm 3 /hr by using nuclear heat (10MW, 905 deg. C) supplied from the HTTR. The safety principle and criteria are also being investigated for the HTTR hydrogen production system. A facility for an out-of-pile test prior to the demonstration test with the HTTR hydrogen production system is under manufacturing to carry out tests of safety, controllability and performance. The out-of-pile test facility simulates key components downstream an intermediate heat exchanger of the HTTR hydrogen production system on a scale of 1 to 30. The tests will be started in 2001 and continued for 4 years or longer. In parallel to the tests, a hydrogen/tritium permeation test and a corrosion test of a catalyst tube of a steam reformer are being carried out to obtain data necessary for the design of the HTTR hydrogen production system. A kind of thermochemical method called IS process is under studying to produce hydrogen from water by

TIT reactor laboratory course using JAERI and PNC large experimental facilities

International Nuclear Information System (INIS)

Sekimoto, Hiroshi; Obara, Toru; Ohtani, Nobuo.

1995-01-01

This report is presented on a reactor laboratory course for graduate students using large facilities in national laboratories in Japan. A reactor laboratory course is offered every summer since 1990 for all graduate students in the Nuclear Engineering Course in Tokyo Institute of Technology (TIT), where the students can choose one of the experiments prepared at Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC) and Research Reactor Institute, Kyoto University (KUR). Both JAERI and PNC belong to Science and Technology Agency (STA). This is the first university curriculum of nuclear engineering using the facilities owned by the STA laboratories. This type of collaboration is promoted in the new Long-Term Program for Research, Development and Utilization of Nuclear Energy adopted by Atomic Energy Commission. Most students taking this course reported that they could learn so much about reactor physics and engineering in this course and the experiment done in large laboratory was a very good experience for them. (author)

Development of seismic risk analysis methodologies at JAERI

International Nuclear Information System (INIS)

Tanaka, T.; Abe, K.; Ebisawa, K.; Oikawa, T.

1988-01-01

The usefulness of probabilistic safety assessment (PSA) is recognized worldwidely for balanced design and regulation of nuclear power plants. In Japan, the Japan Atomic Energy Research Institute (JAERI) has been engaged in developing methodologies necessary for carrying out PSA. The research and development program was started in 1980. In those days the effort was only for internal initiator PSA. In 1985 the program was expanded so as to include external event analysis. Although this expanded program is to cover various external initiators, the current effort is dedicated for seismic risk analysis. There are three levels of seismic PSA, similarly to internal initiator PSA: Level 1: Evaluation of core damage frequency, Level 2: Evaluation of radioactive release frequency and source terms, and Level 3: Evaluation of environmental consequence. In the JAERI's program, only the methodologies for level 1 seismic PSA are under development. The methodology development for seismic risk analysis is divided into two phases. The Phase I study is to establish a whole set of simple methodologies based on currently available data. In the Phase II, Sensitivity study will be carried out to identify the parameters whose uncertainty may result in lage uncertainty in seismic risk, and For such parameters, the methodology will be upgraded. Now the Phase I study has almost been completed. In this report, outlines of the study and some of its outcomes are described

Use of the Power Burst Facility for boron neutron capture therapy

International Nuclear Information System (INIS)

Crocker, J.G.; Griebenow, M.L.; Leatham, J.

1990-01-01

A program is under development at the Idaho National Engineering Laboratory (INEL) that involves using the Power Burst Facility (PBF) for research into boron neutron capture therapy (BNCT). BNCT utilizes the ionizing energy from boron-neutron capture to stop reproduction of or destroy cells in cancerous tissue in a two-step process. The first step is to selectively concentrate a boron isotope within the tumor cell, that when activated by neutron capture emits highly ionizing, short range particles. The second step involves activation of the isotope only in the vicinity of the tumor with a narrow neutron beam. The ( 10 B[n, 4 He] 7 Li) reaction with thermal neutrons produces fission products with track lengths approximately equal to a cell diameter. The INEL program includes the modification of the PBF by the addition of a filter and treatment area. The filter will down-scatter high energy neutrons into the epithermal range and remove thermal neutrons and excessively damaging gamma components. The intense source of epithermal neutrons from PBF is considered necessary to achieve optimum therapy for deep-seated tumors with minimum damage to surface tissue. THe neutron filter conceptualized for PBF utilizes aluminum and heavy water to down-scatter neutrons into the proper energy range. Bismuth will be used for gamma shielding and cadmium will remove the thermal neutron contaminant from the beam. The INEL program leads to human clinical trials at PBF which are intended to prove that brain tumors can be successfully treated through noninvasive techniques. Further research into BNCT at PBF for other cancer types is also anticipated

Proceeding of the second steering conference relating to the 'agreement on the Implementation of Research at the Chernobyl Center for International Research' between CHECIR and JAERI

International Nuclear Information System (INIS)

Nagaoka, Toshi; Togawa, Orihiko; Moriuchi, Shigeru; Rybalko, S.I.; Sukhoruchkin, A.K.; Kazakov, S.V.

1994-11-01

On June, 1992, JAERI and CHECIR concluded an agreement on the Implementation of Research at the Chernobyl Center for International Research (CHECIR). Based on the agreement, JAERI started 'Study on Assessment and Analysis of Environmental Radiological Consequences and Verification of an Assessment System.' CHECIR and JAERI make it a rule to hold steering conference twice a year in order to ensure mutual understanding and exchange of opinion because it its indispensable for smooth and effective implementation of this project. The first steering conference in Japan was held in February of 1994, and three research leaders of CHECIR side were invited from Ukraine. At that time, they gave lectures concerning the environmental Headquarter of JAERI. Progress reports on subject-1 and subject-2 were given from JAERI side at the steering conference. The 5 of presented papers are indexed individually. (author)

Distribution of exogenous porphyrins in vivo; implications for neutron capture therapy

International Nuclear Information System (INIS)

Fairchild, R.G.; Gabel, D.; Hillman, M.; Watts, K.

1982-01-01

Endogenous porphyrins (HpD) are already in clinical use for phototherapy, in which red light is used to stimulate a cytotoxic response in tumors. The evident success, at least with superficial cancers, gives biological evidence of selective concentrations of porphyrins in tumors adequate for therapy. The authors have investigated, in addition, the biodistribution of a synthetic porphyrin (tetraphenylporphinesulfonate, or TPPS) in seven different animal tumor models. Their data, as well as those of others, indicate abundant accumulations of TPPS in tumor. If boronated analogs behave in the same way, boron concentrations would be up to 10 times that needed for therapy. Utilization of such porphyrin analogs in the neutron capture therapy (NCT) procedure is similar in concept to phototherapy currently being used clinically, with the distinct advantage of deeper tissue penetration produced by the activating neutrons

Possible alternation of the blood-brain barrier by boron-neutron capture therapy

International Nuclear Information System (INIS)

Hatanaka, H.; Moritani, M.; Camillo, M.

1991-01-01

In the course of re-assessment of boron-neutron capture therapy (BNCT) for malignant brain tumors, fractionation of neutron irradiation has been proposed. The authors have used BNCT with a single fraction technique during the past 21 years and now decided to study some effects of fractionation. Twenty-two healthy mouse brains were irradiated with thermal neutrons after boron-10 injection (mercaptoundecahydrododecaborate). A second dose of boron-10 was administered and its uptake in the boron-neutron-capture-irradiated brains was determined. A tendency towards increased boron uptake in the moderately BNCT-treated brains was noticed, which may result in increased brain damage if fractionated neutron irradiation is used. (orig.)

A colorimetric determination of boron in biological sample for boron neutron capture therapy

International Nuclear Information System (INIS)

Camilo, M.A.P.; Tomac Junior, U.

1989-01-01

The boron neutron capture therapy (BNCT) has shown better prognosis in the treatment of gliomas and glioblastomas grade III and IV than other therapies. During the treatment of levels of Na 2 10 B 12 H 11 S H must be known in several compartments of the organism and with this purpose the method of colorimetric determination of boron using curcumin was established. This method is simples, reproducible and has adequate sensitivity for this control. (author). 7 refs, 3 figs, 1 tab

Transport calculation of thermal and cold neutrons using NMTC/JAERI-MCNP4A code system

International Nuclear Information System (INIS)

Iga, Kiminori; Takada, Hiroshi; Nagao, Tadashi.

1998-01-01

In order to investigate the applicability of the NMTC/JAERI-MCNP4A code system to the neutronics design study in the neutron science research project of JAERI, transport calculations of thermal and cold neutrons are performed with the code system on a spallation neutron source composed of light water cooled tantalum target with a moderator and a reflector system. The following neutronic characteristics are studied in the calculation : the variation of the intensity of neutrons emitted from a light water moderator or a liquid hydrogen with/without the B 4 C decoupler, which are installed to produce sharp pulse, and that dependent on the position of external source neutrons in the tantalum target. The calculated neutron energy spectra are reproduced well by the semi-empirical formula with the parameter values reliable in physical meanings. It is found to be necessary to employ proper importance sampling technique in the statistics. It is confirmed from this work that the NMTC/JAERI-MCNP4A code system is applicable to the neutronics design study of spallation neutron sources proposed for the neutron science research project. (author)

Transport calculation of thermal and cold neutrons using NMTC/JAERI-MCNP4A code system

Energy Technology Data Exchange (ETDEWEB)

Iga, Kiminori [Kyushu Univ., Fukuoka (Japan); Takada, Hiroshi; Nagao, Tadashi

1998-01-01

In order to investigate the applicability of the NMTC/JAERI-MCNP4A code system to the neutronics design study in the neutron science research project of JAERI, transport calculations of thermal and cold neutrons are performed with the code system on a spallation neutron source composed of light water cooled tantalum target with a moderator and a reflector system. The following neutronic characteristics are studied in the calculation : the variation of the intensity of neutrons emitted from a light water moderator or a liquid hydrogen with/without the B{sub 4}C decoupler, which are installed to produce sharp pulse, and that dependent on the position of external source neutrons in the tantalum target. The calculated neutron energy spectra are reproduced well by the semi-empirical formula with the parameter values reliable in physical meanings. It is found to be necessary to employ proper importance sampling technique in the statistics. It is confirmed from this work that the NMTC/JAERI-MCNP4A code system is applicable to the neutronics design study of spallation neutron sources proposed for the neutron science research project. (author)

Ultrastructural changes in tumor cells following boron neutron capture therapy

International Nuclear Information System (INIS)

Barkla, D.H.; Brown, J.K.; Meriaty, H.; Allen, B.J.

1992-01-01

In a previous study the authors reported on morphological changes in two human melanoma cell lines treated with 10 B-phenylalanine(BPA) and Boron Neutron Capture Therapy(BNCT). The present study describes morphological changes in melanoma and glioma cell lines treated with boron-tetraphenyl porphyrin(BTPP) and BNCT. Porphyrin compounds are selectively taken up by tumor cells and have been used clinically in phototherapy treatment of cancer patients. Boronated porphyrins show good potential as therapeutic agents in BNCT treatment of human cancer patients

Annual report on neutron scattering studies in JAERI, July, 1976 - June, 1977

International Nuclear Information System (INIS)

Hamaguchi, Yoshikazu; Iizumi, Masashi; Endoh, Yasuo

1977-11-01

Neutron scattering studies carried out by Division of Physics, JAERI and by several universities utilizing facilities in Tokai are reported for the period of July, 1976 to June, 1977. The report contains 39 short papers submitted by authors on their individual studies. (auth.)

Present status of low-Z coating development in JAERI

International Nuclear Information System (INIS)

Nakamura, K.; Abe, T.; Obara, K.; Murakami, Y.

1986-01-01

In the JT-60 at JAERI, TiC-coated molybdenum and TiC-coated Inconel tiles are currently used as plasma interactive components. They have already been subjected to initial ohmic heating experiments and exhibited good adhesion characteristics under high heat flux conditions. The present article reviews a JAERI's coating development program for JT-60 experiments currently under way and for the next-step experiments. The program includes development and performance tests of the TiC-coated tiles, development of an in-situ coating technique for the repair of damaged surface of the tiles, and research on carbonization. Stress is laid on thermal shock and thermal fatigue tests of these coatings. In the thermal tests, adhesion between low-Z coatings and bulk materials have been investigated under high heat irradiation. TiC and TiN are used as coating material while Mo and Inconel 625 are employed as bulk material. Results are shown in this report concerning calculated temperature elavation of TiC/TiN/Mo due to hydrogen beam irradiation. As regards the irradiation time required for the melting of the substrate, experimental results mostly agree with calculations. Almost all coatings investigated are not exfoliated from the substrate until the melting of the substrate. (Nogami, K.)

Physics of epi-thermal boron neutron capture therapy (epi-thermal BNCT).

Science.gov (United States)

Seki, Ryoichi; Wakisaka, Yushi; Morimoto, Nami; Takashina, Masaaki; Koizumi, Masahiko; Toki, Hiroshi; Fukuda, Mitsuhiro

2017-12-01

The physics of epi-thermal neutrons in the human body is discussed in the effort to clarify the nature of the unique radiologic properties of boron neutron capture therapy (BNCT). This discussion leads to the computational method of Monte Carlo simulation in BNCT. The method is discussed through two examples based on model phantoms. The physics is kept at an introductory level in the discussion in this tutorial review.

In vivo evaluation of neutron capture therapy effectivity using calcium phosphate-based nanoparticles as Gd-DTPA delivery agent.

Science.gov (United States)

Dewi, Novriana; Mi, Peng; Yanagie, Hironobu; Sakurai, Yuriko; Morishita, Yasuyuki; Yanagawa, Masashi; Nakagawa, Takayuki; Shinohara, Atsuko; Matsukawa, Takehisa; Yokoyama, Kazuhito; Cabral, Horacio; Suzuki, Minoru; Sakurai, Yoshinori; Tanaka, Hiroki; Ono, Koji; Nishiyama, Nobuhiro; Kataoka, Kazunori; Takahashi, Hiroyuki

2016-04-01

A more immediate impact for therapeutic approaches of current clinical research efforts is of major interest, which might be obtained by developing a noninvasive radiation dose-escalation strategy, and neutron capture therapy represents one such novel approach. Furthermore, some recent researches on neutron capture therapy have focused on using gadolinium as an alternative or complementary for currently used boron, taking into account several advantages that gadolinium offers. Therefore, in this study, we carried out feasibility evaluation for both single and multiple injections of gadolinium-based MRI contrast agent incorporated in calcium phosphate nanoparticles as neutron capture therapy agent. In vivo evaluation was performed on colon carcinoma Col-26 tumor-bearing mice irradiated at nuclear reactor facility of Kyoto University Research Reactor Institute with average neutron fluence of 1.8 × 10(12) n/cm(2). Antitumor effectivity was evaluated based on tumor growth suppression assessed until 27 days after neutron irradiation, followed by histopathological analysis on tumor slice. The experimental results showed that the tumor growth of irradiated mice injected beforehand with Gd-DTPA-incorporating calcium phosphate-based nanoparticles was suppressed up to four times higher compared to the non-treated group, supported by the results of histopathological analysis. The results of antitumor effectivity observed on tumor-bearing mice after neutron irradiation indicated possible effectivity of gadolinium-based neutron capture therapy treatment.

Local control of murine melanoma xenografts in nude mice by neutron capture therapy

International Nuclear Information System (INIS)

Allen, B.J.; Corderoy-Buck, S.; Moore, D.E.; Mishima, Y.; Ichihashi, M.

1992-01-01

In recent years considerable progress has been made in the development and implementation of neutron capture therapy (NCT) for the treatment of cancer. In particular, the boron analogue of the melanin precursor phenylalanine, i.e., DL-p-boronophenylalanine (BPA), has been used to demonstrate the regression and cure of Harding-Passey (HP) melanoma in syngeneic mice. However, 18 to 25% cures were obtained for neutron irradiations without boron, suggesting that the neutron dose alone plays an important role. Neutron capture therapy of B-16 melanoma xenografts in nude mice showed substantial tumor regression over 35 days, but the survival rate of NCT treated mice after 7 weeks was only 40-60%. In this paper the authors demonstrate the equivalence of the nude mouse model with a syngeneic model, using the same Harding-Passey murine melanoma line, and delineate the conditions required for maximum differential response between neutron irradiation with and without BPA administration, with complete local control as the end point

Characterization and evaluation studies on some JAERI dosimetry systems

International Nuclear Information System (INIS)

Kojima, T.; Sunaga, H.; Tachibana, H.; Takizawa, H.; Tanaka, R.

2000-01-01

Characterization and evaluation studies were carried out on some JAERI dosimetry systems, mainly alanine-ESR, in terms of the influence on the dose response of parameters such as orientation at ESR analysis, and the temperature during irradiation and analysis. Feasibility study for application of these dosimetry systems to electrons with energies lower than 4 MeV and bremsstrahlung (X rays) was also performed parallel to their reliability check through international dose intercomparison. (author)

Research in JAERI on the backend of nuclear fuel cycle

International Nuclear Information System (INIS)

Maeda, Mitsuru; Takeshita, Isao

1999-01-01

Japan's policy of the backend of nuclear fuel cycle is to reprocess spent fuels and recycle recovered plutonium and uranium, under the principle of no surplus plutonium. High-level radioactive waste separated during reprocessing will be disposed of after solidification in vitrified form, followed by the storage for 30 to 50 years and finally by ultimate disposal in a deep geological formation. The role of JAERI and the effective utilization of NUCEF would become more important. The current status of JAERI's research on backend cycle is reviewed together with the future research direction with emphases on NUCEF utilization. (1) Major objectives of safety research is to develop safety criteria and establish technical bases for licensing, to improve the safety of current or near future technology and to clarify the safety margin of licensed technology. (2) The present goal of fundamental research is to show or clarify the chemical or scientific feasibility of advanced system such as for recycling minor actinides or for incinerating long-lived nuclides. (3) Supporting research for nuclear material control is also conducted mainly for international contribution to strengthened safeguards by IAEA and to frame working of international monitoring system for CTBT. (J.P.N.)

Research on neutron capture therapy in the USSR

International Nuclear Information System (INIS)

Ryabukhin, Y.

1988-01-01

Research on neutron capture therapy in the USSR began in 1964. Towards 1975 prime knowledge in physics, pharmacology and radiobiology had been accumulated. It was realized that inherent to NCT is a variety of modalities as to the type and location of the tumor, the energy and source of neutrons, the nature and transportation of the nuclide-carrying agent (NCA), etc. Thus, it became likely that some modalities would turn out to be clinically feasible. At the end of the 70s, studies of boron derivatives began at the All-Union Oncological Research Center, Moscow. These studies were stimulated by the clinical trials in Japan. Still, neutron capturing nuclides (NCN) other than 10 b are regarded as promising. Research was aimed at clinical trials that could ensure sufficient safety, convenience and conclusiveness. Hence, new requirements emerged, such as the pre-clinical modeling of NCT in big animals and the monitoring of tumor response to each fraction of NCT. Usual requirements are also to be met, that is: tailoring neutron beams with an adequate intensity and energy, choosing NCNs and finding suitable NCAs, physical and radiobiological planning including adoption of tentative RBEs and time-fractionation regimen, selecting tumors as candidates for NCT, and developing techniques for monitoring NCNs in vivo

A colorimetric determination of boron in biological sample for boron neutron capture therapy (BNCT)

International Nuclear Information System (INIS)

Camillo, M.A.P.; Tomac Junior, U.

1990-01-01

The boron neutron capture therapy (BNCT) has shown better prognosis in the treatment of glyemas and gluoblastomas grade III and IV than other therapies. During the treatment the levels of Na 2 10 B 12 H 11 SH must be known in several compartiments of the organism and with this purpose the method of colorimetric determination of boron using curcumine was established. This method is simple, reprodutible and adequate sensitivity for this control. (author) [pt

Report of the third seminar on nuclear physics at the energy region of the JAERI tandem-booster accelerator February 27-28, 1992, Tokai, Japan

International Nuclear Information System (INIS)

Iwamoto, Akira; Oshima, Masumi; Ikezoe, Hiroshi; Nagame, Yuichiro; Shinohara, Nobuo

1992-09-01

A seminar on new experiments to be studied and new experimental apparatus suitable for the JAERI tandem-booster accelerator being under construction was held at Tokai Research Establishment of JAERI in the period from February 27 to 28, 1992. Sixty eight participants from universities and from JAERI attended to discuss the following items: 1. Physics at low temperature, 2. Nuclear structure at high spin and at high excitation energy, 3. Application of unstable beam and their spectroscopy, 4. Nuclear reaction at intermediate energy, 5. New facilities. (author)

Boron compounds in neutron capture therapy of tumors

International Nuclear Information System (INIS)

Strouf, O.; Gregor, V.

1986-01-01

In the selective incorporation of a sufficient amount of a compound containing boron isotope 10 B in the tumor tissue for neutron capture therapy, high efficiency is achieved in tumor destruction while sparing the surrounding tissues. In the treatment of brain tumors, 4-carboxy phenylboric acid and the disodium salt of mercaptoundecahydrododecaborate were successfully tested. The use of the compounds minimizes radiation damage to the blood stream of the brain. In case of melanomas the L-DOPA-borate complex, boronophenylalanine and chlorpromazine preparations containing 10 B are used. In the treatment of cancer of the reproductive organs, boron derivatives of estradiol and testosterone have been proven. The immunobiological procedure, i.e., the use of antibodies with bound boron compounds, is being intensively studied. (M.D.)

HRB-22 capsule irradiation test for HTGR fuel. JAERI/USDOE collaborative irradiation test

Energy Technology Data Exchange (ETDEWEB)

Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kousaku [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

1998-03-01

As a JAERI/USDOE collaborative irradiation test for high-temperature gas-cooled reactor fuel, JAERI fuel compacts were irradiated in the HRB-22 irradiation capsule in the High Flux Isotope Reactor at the Oak Ridge National Laboratory (ORNL). Postirradiation examinations also were performed at ORNL. This report describes 1) the preirradiation characterization of the irradiation samples of annular-shaped fuel compacts containing the Triso-coated fuel particles, 2) the irradiation conditions and fission gas releases during the irradiation to measure the performance of the coated particle fuel, 3) the postirradiation examinations of the disassembled capsule involving visual inspection, metrology, ceramography and gamma-ray spectrometry of the samples, and 4) the accident condition tests on the irradiated fuels at 1600 to 1800degC to obtain information about fuel performance and fission product release behavior under accident conditions. (author)

Overview of severe accident research at JAERI

International Nuclear Information System (INIS)

Sugimoto, Jun

1999-01-01

Severe accident research at JAERI aims at the confirmation of the safety margin, the quantification of the associated risk, and the evaluation of the effectiveness of the accident management measures of the nuclear power reactors, in accordance with the government five-year nuclear safety research program. JAERI has been conducting a wide range of severe accident research activities both in experiment and analysis, such as melt coolant interactions, fission product behaviors in coolant system, containment integrity and assessment of accident management measures. Molten core/coolant interaction and in-vessel molten coolability have been investigated in ALPHA Program. MUSE experiments in ALPHA Program has been conducted for the precise energy measurement due to steam explosion in melt jet and stratified geometries. In VEGA Program, which aims at FP release from irradiated fuels at high temperature and high pressure under various atmospheric conditions, the facility construction is almost completed. In WIND Program the revaporization of aerosols due to decay heating and also the integrity of the piping from this heat source are being investigated. Code development activities are in progress for an integrated source term analysis with THALES, fission product behaviors with ART, steam explosion with JASMINE, and in-vessel debris behaviors with CAMP. The experimental analyses and reactor application have made progress by participating international standard problem and code comparison exercises, along with the use of introduced codes, such as SCDAP/RELAP5 and MELCOR. The outcome of the severe accident research will be utilized for the evaluation of more reliable severe accident scenarios, detailed implementation of the accident management measures, and also for the future reactor development, basically through the sophisticated use of verified analytical tools. (author)

JAERI electrostatic accelerators for multiple ion beam application

International Nuclear Information System (INIS)

Ishii, Yasuyuki; Tajima, Satoshi; Takada, Isao

1993-01-01

An electrostatic accelerators facility of a 3MV tandem accelerator, a 3MV single-ended accelerator and a 400kV ion implanter was completed mainly for materials science and biotechnology research at JAERI, Takasaki. The accelerators can be operated simultaneously for multiple beam application in triple and dual beam modes. The single-ended machine was designed to satisfy an extremely high voltage stability of ±1x10 -5 to provide a submicron microbeam stably. The measured voltage stability and ripple were within the designed value. (author)

Development of radioisotope production in JAERI

International Nuclear Information System (INIS)

Yamabayashi, H.; Kato, H.; Umezawa, H.

1992-01-01

Since 1962, we have been developing methods and technology for producing a wide variety of processed radioisotopes and sealed radiation sources by using the JAERI's reactors, JRR-2, JRR-3, JRR-4 and JMTR, and providing the products to domestic users. At present, 29 nuclides and 31 products are on our list of processed radioisotopes. Some of those isotopes such as P-32, S-35, Cr-51 and short-lived nuclides are being produced regularly for distribution, but most of the rest are produced upon request. The radiation sources of Co-60 needles and Ir-192 pellets for industrial use and Gd-153 pellet, 7 kinds of Ir-192 and Au-198 grain for medical applications are produced and distributed routinely. (author)

Progress report on JAERI-ORNL cooperative neutron scattering research

International Nuclear Information System (INIS)

Iizumi, Masashi

1985-08-01

One year activities done under the JAERI-DOE(ORNL) cooperative neutron scattering program are summarized. This period just followed the completion of the wide-angle neutron diffractometer dedicated to the cooperative research. The report contains results of the performance test of the instrument and early research activities. The latter part includes the time-resolved measurements of the transition kinetics in tin and Ni-Mn alloy as well as the single-crystal diffraction by the flat-cone method. (author)

Analytical dosimetry for spontaneous tumor dogs receiving boron neutron capture therapy

International Nuclear Information System (INIS)

Wheeler, F.J.; Atkinson, C.A.; Gavin, P.R.

1992-01-01

The dog irradiation project of the Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program is administered by Washington State University (WSU) with analytical and physical dosimetry provided by the Idaho National Engineering Laboratory (INEL). One subtask of this project includes BNCT safety studies for dogs with spontaneously-occurring brain tumors. The boron compound (Na 2 B 12 H 11 SH or BSH) was administered and single irradiations performed using the epithermal-neutron beam at the Brookhaven Medical Research Reactor (BMRR). The main goal of the study was not to provide therapy, but to determine tumorcidal effect while administering a subtolerance dose to healthy tissue. Irradiation times were based on delivery of 19 Gy peak physical dose to the blood

Proceedings of workshop on 'boron science and boron neutron capture therapy'

Energy Technology Data Exchange (ETDEWEB)

Kitaoka, Y. [ed.

1998-12-01

This volume contains the abstracts and programs of the 8th (1996), 9th (1997) and 10th (1998) of the workshop on 'the Boron Science and Boron Neutron Capture Therapy' and the recent progress reports especially subscribed. The 11 of the presented papers are indexed individually. (J.P.N.)

Boron neutron capture therapy of malignant brain tumors at the Brookhaven Medical Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Joel, D.D.; Coderre, J.A.; Chanana, A.D. [Brookhaven National Lab., Upton, NY (United States). Medical Dept.

1996-12-31

Boron neutron capture therapy (BNCT) is a bimodal form of radiation therapy for cancer. The first component of this treatment is the preferential localization of the stable isotope {sup 10}B in tumor cells by targeting with boronated compounds. The tumor and surrounding tissue is then irradiated with a neutron beam resulting in thermal neutron/{sup 10}B reactions ({sup 10}B(n,{alpha}){sup 7}Li) resulting in the production of localized high LET radiation from alpha and {sup 7}Li particles. These products of the neutron capture reaction are very damaging to cells, but of short range so that the majority of the ionizing energy released is microscopically confined to the vicinity of the boron-containing compound. In principal it should be possible with BNCT to selectively destroy small nests or even single cancer cells located within normal tissue. It follows that the major improvements in this form of radiation therapy are going to come largely from the development of boron compounds with greater tumor selectivity, although there will certainly be advances made in neutron beam quality as well as the possible development of alternative sources of neutron beams, particularly accelerator-based epithermal neutron beams.

Boron neutron capture therapy of malignant brain tumors at the Brookhaven Medical Research Reactor

International Nuclear Information System (INIS)

Joel, D.D.; Coderre, J.A.; Chanana, A.D.

1996-01-01

Boron neutron capture therapy (BNCT) is a bimodal form of radiation therapy for cancer. The first component of this treatment is the preferential localization of the stable isotope 10 B in tumor cells by targeting with boronated compounds. The tumor and surrounding tissue is then irradiated with a neutron beam resulting in thermal neutron/ 10 B reactions ( 10 B(n,α) 7 Li) resulting in the production of localized high LET radiation from alpha and 7 Li particles. These products of the neutron capture reaction are very damaging to cells, but of short range so that the majority of the ionizing energy released is microscopically confined to the vicinity of the boron-containing compound. In principal it should be possible with BNCT to selectively destroy small nests or even single cancer cells located within normal tissue. It follows that the major improvements in this form of radiation therapy are going to come largely from the development of boron compounds with greater tumor selectivity, although there will certainly be advances made in neutron beam quality as well as the possible development of alternative sources of neutron beams, particularly accelerator-based epithermal neutron beams

Long-survivors of glioblatoma treated with boron neutron capture therapy (BNCT)

International Nuclear Information System (INIS)

Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, H.

2011-01-01

The purpose of this study was to compare the radiation dose between long-survivors and non-long-survivors in patients with glioblatoma (GBM) treated with boron neutron capture therapy (BNCT). Among 23 GBM patients treated with BNCT, there were five patients who survived more than three years after diagnosis. The physical and weighted dose of the minimum gross tumor volume (GTV) of long-survivors was much higher than that of non-long survivors with significant statistical differences.

Universal algorithm for diagnosis of biventricular capture in patients with cardiac resynchronization therapy.

Science.gov (United States)

Jastrzebski, Marek; Kukla, Piotr; Fijorek, Kamil; Czarnecka, Danuta

2014-08-01

An accurate and universal method for diagnosis of biventricular (BiV) capture using a standard 12-lead electrocardiogram (ECG) would be useful for assessment of cardiac resynchronization therapy (CRT) patients. Our objective was to develop and validate such an ECG method for BiV capture diagnosis that would be independent of pacing lead positions-a major confounder that significantly influences the morphologies of paced QRS complexes. On the basis of an evaluation of 789 ECGs of 443 patients with heart failure and various right ventricular (RV) and left ventricular (LV) lead positions, the following algorithm was constructed and validated. BiV capture was diagnosed if the QRS in lead I was predominantly negative and either V1 QRS was predominantly positive or V6 QRS was of negative onset and predominantly negative (step 1), or if QRS complex duration was capture. The algorithm showed good accuracy (93%), sensitivity (97%), and specificity (90%) for detection of loss of LV capture. The performance of the algorithm did not differ among apical, midseptal, and outflow tract RV lead positions and various LV lead positions. LV capture leaves diagnostic hallmarks in the fused BiV QRS related to different vectors of depolarization and more rapid depolarization of the ventricles. An accurate two-step ECG algorithm for BiV capture diagnosis was developed and validated. This algorithm is universally applicable to all CRT patients, regardless of the positions of the pacing leads. ©2014 Wiley Periodicals, Inc.

Help system for control of JAERI FEL (Free Electron laser)

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

1993-01-01

The control system of JAERI FEL (Free Electron Laser) has a help system to provide the information necessary to operate the machine and to develop the new user interface. As the control software is constructed on the MS-Windows 3.x, the hyper-text feature of the Windows help system can be accessed. It consists of three major parts: (1) on-line help, (2) full document, and (3) tutorial system. (author)

Knowledge based operation assist system for JAERI AVF cyclotron

International Nuclear Information System (INIS)

Agematsu, T.; Okumura, S.; Yokota, W.; Arakawa, K.; Murakami, T.; Okamura, T.

1992-01-01

We have developed two operation assist systems for easy and rapid operation of the JAERI AVF cyclotron. One is a knowledge based expert system guiding the sequence of parameter adjustment to inexperienced cyclotron operators. The other is a real-time simulation of the beam trajectories which are calculated from actual operating parameters. It graphically indicates feasible setting range of parameters that satisfies the acceptance of the cyclotron. These systems provide a human interface to adjust the parameters of the cyclotron. (author)

JAERI Fuel Cleanup System (J-FCU) stand-alone tritium test at the TSTA

International Nuclear Information System (INIS)

Konishi, Satoshi; Hayashi, Takumi; Inoue, Masahiko

1993-03-01

JAERI designed, fabricated, and installed the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting tritium free impurities. After a lot of deuterium tests, a first tritium test of the J-FCU was performed with one gram of tritium at the TSTA on June 1991. Main purpose of this test was to evaluate the total integrity and function of the J-FCU system with a DT mixture. Through this test, the J-FCU was operated well and its function with tritium was demonstrated. This report describes the detail test results of the J-FCU first tritium test and discuss its functions by stand-alone mode. Residual tritium inventory of the J-FCU system was also discussed. (author)

Report of the International Review Committee of the joint proposal of the Japan Hadron Facility (KEK) and the Neutron Science Project (JAERI)

International Nuclear Information System (INIS)

1999-08-01

The International Review Committee composed of twelve Japanese and foreign experts was set up under the Research Evaluation Committee of JAERI, and has reviewed the proposed joint project combining JAERI's Neutron Science Project and KEK's Japan Hadron Facility into one major facility. The review meeting took place on April 26-27, 1999, at JAERI Head quarters, Tokyo. According to the points of review given in advance, the review was implemented based on the joint project report submitted and presentations of both institutions. The Research Evaluation Committee received the review report and its explanations from the Review Committee on July 5. The Research Evaluation Committee has acknowledged appropriateness of the review results. This report describes the review results. (author)

Next generation neutron scattering at Neutron Science Center project in JAERI

International Nuclear Information System (INIS)

Yamada, Yasusada; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Katano, Susumu; Aizawa, Kazuya; Suzuki, Jun-ichi; Koizumi, Satoshi; Osakabe, Toyotaka.

1997-01-01

Japan Atomic Energy Research Institute (JAERI) has promoted neutron scattering researches by means of research reactors in Tokai Research Establishment, and proposes 'Neutron Science Research Center' to develop the future prospect of the Tokai Research Establishment. The scientific fields which will be expected to progress by the neutron scattering experiments carried out at the proposed facility in the Center are surveyed. (author)

Current status of JAERI Tokai hot cell facilities

International Nuclear Information System (INIS)

Itami, Hiroharu; Morozumi, Minoru; Yamahara, Takeshi

1992-01-01

JAERI has 4 hot cell facilities in order to examine high radioactive materials. Three of them, the Research Hot Laboratory, the Reactor Fuel Examination Facility and the Waste Safety Testing Facility are located in the JAERI Tokai site, and the rest is the JMTR Hot Laboratory in the Oarai site. The Research Hot Laboratory (RHL) was constructed for post-irradiation examination (PIE), especially nuclear related basic research experiment, such as metallurgical, chemical and mechanical examination on fuels and materials irradiated in research and test reactors. This facility has 10 large dimension concrete and 38 lead cells. At present the RHL is used for various kinds of examinations of high radioactive samples such as fuels of research and test reactors, power reactors and high temperature testing reactor (HTTR), and structural materials. The Reactor Fuel Examination Facility (RFEF) was designed and constructed for carrying out PIE of irradiated full-size fuel assemblies of light water reactors (LWRs). This facility has a storage pool, 8 concrete and 5 lead cells. They are currently used for safety evaluation on high burnup and advanced lWR fuels as part of the national program. The Waste Safety Testing Facility (WASTEF) was designed and constructed for safety research on long-term storage and disposal of high level radioactive wastes, generated by fuel reprocessing. The WASTEF has 5 concrete cells and 1 lead cell. Examinations on the behavior of various long-lived fission products in a glass form and in a canister and, releasing behavior of them out of a canister are carrying out under the condition at storage. (author)

Current status of HTTR project at JAERI

International Nuclear Information System (INIS)

Saito, Shinzo; Sudo, Yukio; Tanaka, Toshiyuki; Baba, Osamu

1992-01-01

The HTTR is a high temperature gas cooled test reactor with thermal output of 30 MW, outlet coolant temperatures of 850degC at rated operation and 950degC at high temperature test operation and primary coolant pressure of 4 MPa. The HTTR consists of a reactor pressure vessel with a prismatic core in it, a primary cooling loop with an intermediate helium-helium heat exchanger and a pressurized water cooler in parallel, an auxiliary cooling system, a reactor vessel cooling system and related components. The HTTR is utilized for establishing and upgrading the technology bases for advanced HTGRs including irradiation tests for fuels and materials, safety demonstration tests for HTGRs and nuclear heat application and for carrying out various kinds of innovative basic researches on high temperature technologies. Since 1969, the JAERI has carried out research and development works on block type fuel, high temperature materials, high temperature in-core instrumentations, high temperature components, reactor physics, heat transfer and fluid dynamics, plate-out of fission products etc., in order to construct the HTTR which can supply high temperature coolant of 950degC to the outside of the pressure vessel for the nuclear heat application, for the first time in the world. In November 1990, the installation permit was issued by the Government through about 20 month safety review by the Science and Technology Agency and Nuclear Safety Commission. The construction of the HTTR facility was initiated on the site in the Oarai Research Establishment, JAERI in March 1991. The excavation of ground is now finished at the HTTR site. It will take about six years for the completion of the HTTR facility and the first criticality will be attained in 1996. (author)

Studies in precise neutron optics at JAERI

International Nuclear Information System (INIS)

Tomimitsu, Hiroshi

1994-01-01

Studies in the field of so-called 'Precise Neutron Optics' at JAERI were reported, since the beginning of 1970. It started with the photographic detection of the 'Pendellusung Fringes' in a wedge-shaped Si crystal, promoted by Prof.K.Kohra. Neutron diffraction topography was also tried and used for the 'direct' observation of the substructure in a Cu-5%Ge single crystal, carried out by the present author. So-called 'VSANS' (Very Small Angle Neutron Scattering) was also tried, with the angular resolution better than 0.1 sec. of arc, for the structural observation of several kinds of 'amorphous' materials, such as neutron-irradiated silica glasses, Pb-containing glasses and several ribbon-shaped amorphous alloys, carried out by Dr.K.Doi. Recently with the co-operation with Prof.S.Kikuta's group, some interferometric experiments were tried, such as the detection of the double-refraction phenomenon of the neutron in the magnetic materials, carried out by Dr.S.Nakatani. The apparatus for precise neutron optics and topography (PNO) was constructed at the JRR-3M in JAERI in 1992, which was just properly made for the studies in the present thema. With the PNO, the characterization of Ni-Ti multilayer mirror for the interferometer with the cold/ ultra-cold neutrons was carried out, the results being reported in the other article of this symposium by Dr.H.Funahashi. Through the test use of the PNO with the neutron interferometry, carried out by Dr.Y.Hasegawa, it was revealed that the PNO is the best facility in the world for the neutron interferometry; with the datas of the count ratio upto 20 cps and the contrast more than 40%. Dr.K.Aizawa is now refining the VSANS-technique on the PNO, for the precise observation of the precipitation behaviour of high density small particles such as metatic alloy-system. (author)

Monte Carlo calculations on efficiency of boron neutron capture therapy for brain cancer

International Nuclear Information System (INIS)

Awadalla, Galaleldin Mohamed Suliman

2015-11-01

The search for ways to treat cancer has led to many different treatments, including surgery, chemotherapy, and radiation therapy. Among these treatments, boron neutron capture therapy (BNCT) has shown promising results. BNCT is a radiotherapy treatment modality that has been proposed to treat brain cancer. In this technique, cancerous cells are being injected with 1 0B and irradiated by thermal neutrons to increase the probability of 1 0B (n, a)7 L i reaction to occur. This reaction can potentially deliver a high radiation dose sufficient to kill cancer cells by concentrating boron in them. The short rang of 1 0B (n, a) 7 L i reaction limits the damage to only cancerous cells without affecting healthy tissues. The effectiveness and safety of radiotherapy are dependent on the radiation dose delivered to the tumor and healthy tissues. In this thesis, after reviewing the basics and working principles of boron neutron capture therapy (BNCT), monte Carlo simulations were carried out to model a thermal neutron source suitable for BNCT and to examine the performance of proposed model when used to irradiate a sample of boron containing both 1 0B and 1 1B isotopes. MCNP5 code was used to examine the modeled neutron source through different shielding materials. The results were presented, analyzed and discussed at the end of the work. (author)

Annual report on neutron scattering studies in JAERI, September 1, 1978 - August 31, 1979

International Nuclear Information System (INIS)

Iizumi, Masashi; Endoh, Yasuo

1980-03-01

Neutron scattering studies carried out from September 1978 to August 1979 by Division of Physics, JAERI, and universities with JRR-2 and -3 neutron beam facilities are described: 51 summary reports, and a list of publications. (author)

The JAERI and Universities joint project research reports on the 4th joint research project between JAERI and Universities on backend chemistry

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-02-01

In the Joint Research Project between JAERI and Universities on Backend Chemistry, the 4th-term researches of it were performed on sixteen themes from April of 1999 to March of 2001 under the four categories, i.e. Nuclear-chemistry and physical-chemistry properties of actinides', 'Solid state chemistry and nuclear fuel engineering of actinides', 'Solution chemistry and technologies for separation and analysis of actinides' and Treatment of radioactive waste and environmental chemistry'. The present report compiled the papers contributed to the Joint Research Project. (author)

Plastic scintillation dosimetry for radiation therapy: minimizing capture of Cerenkov radiation noise

International Nuclear Information System (INIS)

Beddar, A Sam; Suchowerska, Natalka; Law, Susan H

2004-01-01

Over the last decade, there has been an increased interest in scintillation dosimetry using small water-equivalent plastic scintillators, because of their favourable characteristics when compared with other more commonly used detector systems. Although plastic scintillators have been shown to have many desirable dosimetric properties, as yet there is no successful commercial detector system of this type available for routine clinical use in radiation oncology. The main factor preventing this new technology from realizing its full potential in commercial applications is the maximization of signal coupling efficiency and the minimization of noise capture. A principal constituent of noise is Cerenkov radiation. This study reports the calculated capture of Cerenkov radiation by an optical fibre in the special case where the radiation is generated by a relativistic particle on the fibre axis and the fibre axis is parallel to the Cerenkov cone. The fraction of radiation captured is calculated as a function of the fibre core refractive index and the refractive index difference between the core and the cladding of the fibre for relativistic particles. This is then used to deduce the relative intensity captured for a range of fibre core refractive indices and fibre core-cladding refractive index differences. It is shown that the core refractive index has little effect on the amount of radiation captured compared to the refractive index difference. The implications of this result for the design of radiation therapy plastic scintillation dosimeters are considered

The Boron Neutron Capture Therapy (BNCT) Project at the TRIGA Reactor in Mainz, Germany

DEFF Research Database (Denmark)

Hampel, G.; Grunewald, C.; Schütz, C.

2011-01-01

The thermal column of the TRIGA reactor in Mainz is being used very effectively for medical and biological applications. The BNCT (boron neutron capture therapy) project at the University of Mainz is focussed on the treatment of liver tumours, similar to the work performed at Pavia (Italy) a few ...

The Universities and JAERI joint research project. The achievements and prospects

International Nuclear Information System (INIS)

Ohashi, Hiroshi; Nakamura, Takashi; Yamaguchi, Sadaei

1999-01-01

The universities and JAERI joint research project has been carried out since 13 years ago on an equivalent basis with the universities and JAERI and co-ownership of the results. This paper consists of the history and results of research project and evaluation. The significance, characteristics, themes and problems of the project are arranged. The main results and the future of the project are explained. Two large projects such as the backend chemical project and the high-degree application of radiation project have been studied. The backend chemical project consisted of four themes; the nuclear chemical researches for TRU recycle, the solid chemical research of nuclear fuel and waste, new separation method for reprocessing and waste disposal and the fundamental chemical researches for disposal waste. The high-degree application of radiation project have eight themes; effects of ion beam on organism, slow positron generation and its application to materials, ion irradiation effects on polymer materials, nuclear spectroscopy and nuclear physics of isotope using online isotope separator, shield and behavior of accelerator radiation, materials analysis by ion beam, effects of nuclear transformation product by nuclear fusion reactor radiation damage and biofunction analysis of plant using positron release nuclide. (S.Y.)

Project of the JAERI superconducting AVF cyclotron for applications in biotechnology and materials science

International Nuclear Information System (INIS)

Miyawaki, Nobumasa; Kurashima, Satoshi; Okumura, Susumu; Chiba, Atsuya; Agematsu, Takashi; Kamiya, Tomihiro; Kaneko, Hirohisa; Nara, Takayuki; Saito, Yuichi; Ishii, Yasuyuki; Sakai, Takuro; Mizuhashi, Kiyoshi; Fukuda, Mitsuhiro; Yokota, Watalu; Arakawa, Kazuo

2005-01-01

A project for expanding TIARA (Takasaki Ion accelerators for Advanced Radiation Application) facilities of JAERI has been proposed to broaden application region of biotechnology and materials science. As a result of the investigation of TIARA facility user's request, energy increase up to more than 100 MeV/n for heavy ions and up to 300 MeV for proton are strongly required. The magnet of a superconducting AVF cyclotron with a K number of 900 has been designed to cope with acceleration of both 150 MeV/n heavy ions and 300 MeV protons. The lower limit of energies has been investigated to overlap the energy region covered by the JAERI AVF cyclotron, required to increase beam time for present users. We have designed a beam transport system to satisfy various requirements of the applications. (author)

Ex-post evaluation. Research independency of the basic science study of JAERI

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki; Takahashi, Shoji

2010-06-01

A research independency was defined here as the continuity and the development of a corresponding research field with an evolution of history. The authors took three fields as research parameters for the ex-post evaluation. They were all belonged to the basic science field studied in the Japan Atomic Energy Research Institute (JAERI). The first parameter was actinides, which was situated in the center of research networking from the viewpoint of socio-economy. The second parameter was positron, which was situated in the periphery of research networking and the third one was neutron, which had competition with other research organizations in Japan. The three were supported and promoted financially by the JAERI. The target year was covered from 1978 to 2002, a 25-years. INIS (International Nuclear Information Systems) operated by the International Atomic Energy Agency (IAEA) was used as the tool for the present bibliometric study. It was revealed that important factors that led the sustainable success of the research independency were the constant efforts to accomplish their mission, the education of their successors to instructing the explicit and tacit research findings and the construction of intellectual networking with learned circles and industries, those were in good collaboration with JAERI. These were quantitatively clarified. Conversely, main factors that impeded the development of the research independency were discontinuance of research caused by a retirement, a change of post or that of occupation, and an unexpected accident (death) of the core researchers. Among three parameters, the authors confirmed that there occurred the time-dependent stage of germination, development and declination of the research independency attributing to the interaction between the succession factors and impeded factors. For this kind of ex-post evaluation, the support of field research laboratory was inevitable. (author)

The Swedish facility for boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Skoeld, K.; Capala, J. [Studsvik Medical AB (Sweden); Kierkegaard, J.; Haakansson, R. [Studsvik Nuclear AB (Sweden); Gudowska, I. [Karolinska Institute (Sweden)

2000-10-01

A BNCT (Boron Neutron Capture Therapy) facility has been constructed at the R2-0 reactor at Studsvik, Sweden. R2-0 is a 1 MW, open core, pool reactor. The reactor core is suspended on a movable tower and can be positioned anywhere in the pool. The BNCT facility includes two adjacent, parallel filter/moderator configurations and the reactor core is positioned in front of any of them as appropriate. One of the resulting neutron beams has been optimized for clinical irradiations with a filter/moderator system that allows easy variation of the neutron spectrum from the thermal to the epithermal energy range and with an extended collimator for convenient patient positioning. The other beam has been designed for radiobiological research and is equipped with a heavy water moderator and a large irradiation cavity with a uniform field of thermal neutrons. (author)

The Swedish facility for boron neutron capture therapy

International Nuclear Information System (INIS)

Skoeld, K.; Capala, J.; Kierkegaard, J.; Haakansson, R.; Gudowska, I.

2000-01-01

A BNCT (Boron Neutron Capture Therapy) facility has been constructed at the R2-0 reactor at Studsvik, Sweden. R2-0 is a 1 MW, open core, pool reactor. The reactor core is suspended on a movable tower and can be positioned anywhere in the pool. The BNCT facility includes two adjacent, parallel filter/moderator configurations and the reactor core is positioned in front of any of them as appropriate. One of the resulting neutron beams has been optimized for clinical irradiations with a filter/moderator system that allows easy variation of the neutron spectrum from the thermal to the epithermal energy range and with an extended collimator for convenient patient positioning. The other beam has been designed for radiobiological research and is equipped with a heavy water moderator and a large irradiation cavity with a uniform field of thermal neutrons. (author)

JAERI TIARA annual report 1994. V.4. April 1994 - March 1995

Energy Technology Data Exchange (ETDEWEB)

Tanaka, Ryuichi; Seguchi, Tadao; Nashiyama, Isamu [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment; eds.; and others

1995-10-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1994 to March 31, 1995. Summary reports of 86 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author).

JAERI TIARA annual report vol. 3 (1993). April 1993 - March 1994

International Nuclear Information System (INIS)

Ishigaki, Isao; Tanaka, Ryuichi; Seguchi, Tadao

1994-11-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1993 to March 31, 1994. Summary reports of 80 papers and brief descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

JAERI TIARA annual report 1995. V. 5. April 1995 - March 1996

International Nuclear Information System (INIS)

Tanaka, Ryuichi; Seguchi, Tadao; Ohmichi, Hideki

1997-01-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1995 to March 31, 1996. Summary reports of 84 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

JAERI TIARA annual report 1994. V.4. April 1994 - March 1995

International Nuclear Information System (INIS)

Tanaka, Ryuichi; Seguchi, Tadao; Nashiyama, Isamu

1995-10-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1994 to March 31, 1995. Summary reports of 86 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

A proposal for study of ion-beam induced chemical reactions using JAERI tandem accelerator

International Nuclear Information System (INIS)

1985-11-01

Problems in ion-beam induced chemical reactions using JAERI Tandem Accelerator were discussed. Research philosophy, some proposed experiments which are based on measurements during ion-beam bombardment, and main features of the experimental apparatus are briefly described in this report. (author)

Proceedings of second JAERI-JNC joint conference on nuclear safety research

International Nuclear Information System (INIS)

Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

2004-08-01

The second JAERI-JNC Joint Conference on Nuclear Safety Research was held on February 6, 2004 in Tokyo for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety in the New Organization. A total of 259 people participated in the conference mainly from the nuclear industries and regulatory organizations and the number was much larger than that in the last conference of 188. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Higashi, the Nuclear Safety Commissioner, made a special lecture on the radiation protection from the high-level radioactive waste disposal. Finally, a panel discussion was conducted with the title of ''how to conduct efficiently the nuclear safety research in the New Organization'' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from the regulatory organizations, nuclear industry, JAERI and JNC discussed the subject together with the participants on the floor. The panelists not from JAERI and JNC expressed their views and opinions on how to conduct efficiently the nuclear safety research in the New Organization that were valuable inputs for developing

Phase IIC experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics

International Nuclear Information System (INIS)

Youssef, M.Z.

1992-12-01

Effort in Phase IIC of the US/JAERI Collaborative Program on Fusion Neutronics was focused on performing integral experiments and post analyses on blankets that include the actual heterogeneities found in several blanket designs. Two geometrical arrangements were considered for the blanket assembly, namely multi-layers of Li 2 O and beryllium in an edge-on, horizontally alternating configuration for a front depth of 30 cm, followed by the Li 2 O breeding zone (Be edge-on, BEO, experiment), and vertical water coolant channels arrangement (WCC experiment). The objectives are to examine the accuracy of predicting tritium production. In the BEO system, it was shown that, with the zonal method to measure tritium production from natural lithium (Tn), the calculated-to-measured values (C/E) are 0.95-1.05 (JAERI) and 0.98-0.9 (U.S.), which is consistent with the results obtained in other Phases of the Program (Phases IIA and IIb)). In the WCC experiment, there is a noticeable change in C/E values for T 6 near the coolant channels where steep gradients in T 6 production are observed. The C/E values obtained with the Li-foil detectors are on the average closer to unity than those obtained by the Li-glass method. As for T 7 , the values obtained by NE213 method are within ±15% in JAERI's calculations, but larger values (∼20-25%) are obtained in the U.S. calculations due to the differences of cross-sections data files. Around heterogeneities, the prediction accuracy for T 7 is better than for T 6 . (J.P.N.)

JAERI/KEK target material program overview

International Nuclear Information System (INIS)

Kikuchi, Kenji; Kogawa, Hiroyuki; Sasa, Toshinobu

2001-01-01

Mercury target was designed for megawatt neutron scattering facility in JAERI/KEK spallation neutron source. The incident proton energy and current are 3 GeV and 333 μA, respectively: the total proton energy is 1 MW in short pulses at a frequency of 25 Hz. Under the guide rule the mercury target was designed: the maximum temperature of target window is 170degC and induced stresses for the type 316 stainless steel are within limits of design guide. In order to demonstrate ADS (Accelerator Driven Systems) transmutation critical and engineering facilities have been designed conceptually. In engineering facility lead-bismuth spallation target station is to be planned. Objective to build the facility is to demonstrate material irradiation. According to neutronics calculation irradiation damage of the target vessel window will be 5 dpa per year. (author)

Development of inverse-planning system for neutron capture therapy

International Nuclear Information System (INIS)

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Maruo, Takeshi

2006-01-01

To lead proper irradiation condition effectively, Japan Atomic Energy Agency (JAEA) is developing an inverse-planning system for neutron capture therapy (NCT-IPS) based on the JAEA computational dosimetry system (JCDS) for BNCT. The leading methodology of an optimum condition in the NCT-IPS has been applied spatial channel theory with adjoint flux solution of Botzman transport. By analyzing the results obtained from the adjoint flux calculations according to the theory, optimum incident point of the beam against the patient can be found, and neutron spectrum of the beam which can generate ideal distribution of neutron flux around tumor region can be determined. The conceptual design of the NCT-IPS was investigated, and prototype of NCT-IPS with JCDS is being developed. (author)

Comparison and analysis of BNCT radiation dose between gold wire and JCDS measurement

International Nuclear Information System (INIS)

Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, Hiroaki

2006-01-01

We compared and evaluated boron neutron capture therapy (BNCT) radiation dose between gold wire measurement and JAERI Computational Dosimetry System (JCDS). Gold wire analysis demonstrates the actual BNCT dose though it dose not reflect the real the maximum and minimum dose in tumor tissue. We can conclude that JCDS is precise and high-reliable dose planning system for BNCT. (author)

Program of nuclear criticality safety experiment at JAERI

International Nuclear Information System (INIS)

Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Ohnishi, Nobuaki

1983-11-01

JAERI is promoting the nuclear criticality safety research program, in which a new facility for criticality safety experiments (Criticality Safety Experimental Facility : CSEF) is to be built for the experiments with solution fuel. One of the experimental researches is to measure, collect and evaluate the experimental data needed for evaluation of criticality safety of the nuclear fuel cycle facilities. Another research area is a study of the phenomena themselves which are incidental to postulated critical accidents. Investigation of the scale and characteristics of the influences caused by the accident is also included in this research. The result of the conceptual design of CSEF is summarized in this report. (author)

Status of work on superconducting quarter wave resonators at JAERI

International Nuclear Information System (INIS)

Takeuchi, S.

1988-01-01

A superconducting heavy ion linac is being proposed for the JAERI-tandem booster. For the accelerating structure of the tandem booster which ought to accelerate heavy ions of wide range of mass numbers, quarter wave resonator (QWR)s are suitable because of their wide ion-velocity acceptance. Ions of hydrogen to bismuth from the JAERI tandem can be accelerated by β = 0.1 QWRs. The excellent result of a niobium QWR at Argonne National Laboratory was a motive for the development of niobium QWRs. Further considerations on the design were required, because the Argonne's QWR did not have beam ports nor frequency tuners. As a result of considerations on these points, it has been decided to have an oval cylinder for the outer conductor. The prototype resonator has been built and tested. The fabrication techniques of explosive bonding, electron beam welding and heat treatment were found to be available in domestic companies in 1984. After obtaining niobium and niobium-clad-copper materials in 1985, the prototype resonator was built in 1985-86. Electro-polishing was done in their laboratory. Tests at 4.2 K have been repeated several times in combination of treatments of the niobium surface. The work is proceeding to the construction of a buncher and a prototype linac unit which are composed of superconducting QWRs. 4 references, 4 figures, 2 tables

LTFR-4, Library Generated for Fast Reactor Design Program from JAERI Fast-Set Multigroup Constant

International Nuclear Information System (INIS)

Suzuki, Tomoo

1971-01-01

Nature of physical problem solved: The program processes JAERI-Fast group constants sets of less than 30-group and prepares a binary library tape for efficient usage by a series of related fast reactor design calculation programmes

Some thoughts on tolerance, dose, and fractionation in boron neutron capture therapy

International Nuclear Information System (INIS)

Gahbauer, R.; Goodman, J.; Blue, T.

1988-01-01

Unique to boron neutron capture therapy, the tolerance very strongly depends on the boron concentration in normal brain, skin and blood. If one first considers the ideal situation of a 2 KeV beam and a compound clearing from normal tissues and blood, the tolerance dose to epithermal beams relates to the maximum tolerated capture gamma dose and capture high LET dose, H (n,gamma)D and N(n,p) 14 C. The authors can relate this gamma and high LET dose to known clinical experience. Assuming gamma and high LET dose ratios as given by Fairchild and Bond, one may first choose a clearly safe high LET whole brain dose and calculate the unavoidably resulting gamma dose. To a first approximation 500 cGy of high LET dose results in 3,000 cGy gamma dose. One can speculate that this approximates the tolerance of whole brain to the 2 KeV beam with no contributing boron dose if the radiation is fractionated. It would clearly be beyond tolerance in a single fraction where most therapists would be uncomfortable to deliver even one third of the above doses

Response of the oral mucosa to porphyrin mediated boron neutron capture therapy

International Nuclear Information System (INIS)

Morris, G.M.

2003-01-01

Pre-clinical studies are now in progress to develop boron neutron capture therapy (BNCT) modalities for the treatment of head and neck carcinomas. BNCT is a bimodal therapy which involves the administration of a boron-10 enriched compound, that accumulates preferentially in tumours, prior to irradiation with low energy neutrons. These neutrons are captured by boron-10 atoms to produce a highly localised radiation exposure. More recently, it has been demonstrated that various boronated porphyrins can target a variety of tumours. Of the porphyrins evaluated to date, copper tetracarboranylphenyl porphyrin (CuTCPH) is a strong candidate for potential clinical evaluation. It has extremely high specificity for a variety of tumour models. Therapeutic efficacy of CuTCPH mediated BNCT has been demonstrated in pre-clinical studies using the murine EMT-6 carcinoma model. In the present investigation the response of the oral mucosa to CuTCPH mediated boron neutron capture (BNC) irradiation was assessed using a standard rat model (ventral tongue). Single exposure irradiation was carried out on the thermal neutron beam at the Brookhaven Medical Research Reactor, at 3 days after the final injection of the boronated porphyrin. The impact of CuTCPH mediated BNC irradiation on oral mucosa at therapeutically effective exposure times, assessed using the ventral tongue model, was minimal. This was primarily due to the fact that blood boron levels (from CuTCPH) were very low at the time of irradiation. Analysis of the dose-effect data for CuTCPH gave a compound biological effectiveness (CBE) factor of 2.5. It can be concluded that, although, the CBE factor (calculated using blood boron concentrations) was relatively high, CuTCPH mediated BNC irradiation should not cause significant damage at clinically relevant radiation doses. This is because blood boron levels would be very low at the time of irradiation

Final Report: 8th International Symposium on Neutron Capture Therapy (NCT) for Cancer, May 15, 1998 - May 15, 1999

International Nuclear Information System (INIS)

Hawthorne, M.F.

1999-01-01

The 8th International Symposium on Neutron Capture Therapy for Cancer (8th ISNCTC) was held in La Jolla, CA on Sept. 13-18, 1998. This biennial meeting of the International Society for Neutron Capture Therapy (ISNCT) was hosted by Society President M.F. Hawthorne (UCLA Dept. of Chemistry and Biochemistry). The Symposium brought together scientists (300 registrants from 21 countries) from diverse fields to report the latest developments in NCT. Topics of the 275 papers presented (30 plenary lectures, 81 oral presentations, and 164 posters) included the physics of neutron sources, chemistry of tumor-targeting agents, dosimetry, radiobiological studies, and clinical applications

Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1992

International Nuclear Information System (INIS)

1993-08-01

The results of the joint researches by utilizing the facilities of JAERI in 1992 fiscal year were summarized. The number of research themes in 1992 was 247 cases. In this book, 166 reports are collected. (J.P.N.)

Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1993

International Nuclear Information System (INIS)

1994-07-01

The results of the joint researches by utilizing the facilities of JAERI in 1993 fiscal year were summarized. The number of research themes in 1993 was 228 cases. In this book, 243 reports are collected. (J.P.N.)

JNC-JAERI united research report. A study on degradation of structural materials under irradiation environment in nuclear reactors

International Nuclear Information System (INIS)

Hoshiya, Taiji; Takaya, Shigeru; Nagae, Yuji; Aoto, Kazumi; Abe, Yasuhiro; Nakamura, Yasuo; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Ohmi, Masao; Saito, Junichi; Shimizu, Michio

2004-10-01

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in fiscal year 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes because it has been common objective for both Institutes in the research field of structural materials such as Fast Breeder Reactor and Light Water Reactors components. The purpose of the study is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage along grain boundaries. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. The former apparatus, supersensitive Flux Gate sensor was installed, could detector leaked magnetic flux from material damaged by neutron irradiation. The latter one, Atomic Force Microscope was installed, could detect grain boundary corrosion loss after an electrochemical corrosion test of irradiated material. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. As the results of preliminary studies using Ni ion irradiated specimen, damage detection by corrosion property in grain boundary was possible but magnetic property change could not detect. We will start the study on neutron irradiation damage by employing the two apparatus as the next step. (author)

Development of integrated models for energy-economy systems analysis at JAERI

International Nuclear Information System (INIS)

Yasukawa, Shigeru; Mankin, Shuichi; Sato, Osamu; Yonese, Hiromi

1984-08-01

This report, being a revision of the preprint for distribution to participants at IEA/ETSAP Workshop held, at JAERI, Tokyo, March 1984, describes the concept of the integrated models for energy-economy systems analysis now being carried out at JAERI. In this model system, there contains four different categories of computer codes. The first one is a series of computer codes named as E 3 -SD representatively, which are utilized to develop a dynamic scenario generation in a long-term energy economy evolution. The second one, of which the main constituents are the MARKAL, i.e. an optimal energy flow analizer, and the TRANS-I/O, i.e. a multi-sectoral economy analyzer, has been developed for the analysis of structural characteristics embodied in our energy-economy system. The third one is for a strategy analysis on nuclear power reactor installation and fuel cycle development, and its main constituent is the JALTES. The fourth one is for a cost-benefit-risk analysis including various kinds of data bases. As the model system being still under development, but the idea of application of it to such a problem as '' the role of the HTGR in the prospects of future energy supply'' is also explained in the report. (author)

Options for a next generation neutron source for neutron scattering based on the projected linac facility at JAERI

International Nuclear Information System (INIS)

Mezei, F.; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Aizawa, Kazuya; Suzuki, Jun-ichi.

1997-03-01

Japan Atomic Energy Research Institute (JAERI) has a project to construct a high intensity proton accelerator to promote wide basic science using neutrons and nuclear power technologies such as radioactive nuclide transmutation. One of the most important field for utilization of neutron beam is neutron scattering. The energy and the averaged current obtained by the proton accelerator are 1.5 GeV and 4-5.3 mA, respectively and these provide 6-8 MW power. The repetition frequency is 50-60 Hz. Evaluation of options for the use of accelerators for neutron production for neutron scattering research and investigation of the neutron research opportunities offered by sharing the superconducting linac planned at JAERI were discussed. There are two ways of the utilization of proton beams for neutron scattering experiment. One is for long pulse spallation source (LPSS) and the other is for short pulse spallation source (SPSS). Quantitative evaluation of instrument performance with LPSS and SPSS was examined in the intensive discussion, calculations, workshop on this topics with Prof. F. Mezei who stayed at JAERI from October 24 to November 6, 1996. A report of the collaborative workshop will be also published separately. (author)

Initiation of a phase-I trial of neutron capture therapy at the MIT research reactor

International Nuclear Information System (INIS)

Harling, O.K.; Bernard, J.A.; Yam, Chun-Shan

1995-01-01

The Massachusetts Institute of Technology (MIT), the New England Medical Center (NEMC), and Boston University Medical Center (BUMC) initiated a phase-1 trial of boron neutron capture therapy (BNCT) on September 6, 1994, at the 5-MW(thermal) MIT research reactor (MITR). A novel form of experimental cancer therapy, BNCT is being developed for certain types of highly malignant brain tumors such as glioblastoma and melanoma. The results of the phase-1 trials on patients with tumors in the legs or feet are described

Perspectives of boron-neutron capture therapy of malignant brain tumors

Science.gov (United States)

Kanygin, V. V.; Kichigin, A. I.; Krivoshapkin, A. L.; Taskaev, S. Yu.

2017-09-01

Boron neutron capture therapy (BNCT) is characterized by a selective effect directly on the cells of malignant tumors. The carried out research showed the perspective of the given kind of therapy concerning malignant tumors of the brain. However, the introduction of BNCT into clinical practice is hampered by the lack of a single protocol for the treatment of patients and the difficulty in using nuclear reactors to produce a neutron beam. This problem can be solved by using a compact accelerator as a source of neutrons, with the possibility of installation in a medical institution. Such a neutron accelerator for BNCT was developed at Budker Institute of Nuclear Physics, Novosibirsk. A neutron beam was obtained on this accelerator, which fully complies with the requirements of BNCT, as confirmed by studies on cell cultures and experiments with laboratory animals. The conducted experiments showed the relative safety of the method with the absence of negative effects on cell cultures and living organisms, and also confirmed the effectiveness of BNCT for malignant brain tumors.

Further development of thermal neutron capture therapy for metastatic and deeply-invasive human malignant melanoma

International Nuclear Information System (INIS)

Mishima, Yutaka

1995-03-01

This issue is the collection of the papers presented thermal neutron capture therapy for metastatic and deeply-invasive human malignant melanoma. Separate abstracts were prepared for 2 of the papers in this report. The remaining 32 papers were considered outside the subject scope of INIS. (J.P.N.)

Boron neutron capture therapy (BNCT) using fast neutrons: Effects in two human tumor cell lines

International Nuclear Information System (INIS)

Sauerwein, W.; Ziegler, W.; Szypniewski, H.; Streffer, C.

1990-01-01

The results demonstrate that the effect of fast neutrons on cell survival in cell culture can be enhanced by boron neutron capture reaction. Even with lower enhancement ratios, the concept of NCT assisted fast neutron therapy may successfully be applied for tumor treatment with the Essen cyclotron. (orig.)

JAERI/U.S. collaborative program on fusion blanket neutronics

International Nuclear Information System (INIS)

Nakagawa, Masayuki; Mori, Takamasa; Kosako, Kazuaki; Oyama, Yukio; Nakamura, Tomoo

1989-10-01

Phase IIa and IIb experiments of JAERI/U.S. Collaborative Program on Fusion Blanket Neutronics have been performed using the FNS facility at JAERI. The phase IIa experimental systems consist of the Li 2 O test region, the rotating neutron target and the Li 2 CO 3 container. In phase IIb, a beryllium layer is added to the inner wall to investigate a multiplier effect. Measured parameters are source characteristics by a foil activation method and spectrum measurements using both NE-213 and proton recoil counters. The measurements inside the Li 2 O region included tritium production rates, reaction rate by foil activation and neutron spectrum measurements. Analysis for these parameters was performed by using two dimensional discrete ordinate codes DOT3.5 and DOT-DD, and a Monte Carlo code MORSE-DD. The nuclear data used were based on JENDL3/PR1 and PR2. ENDF/B-IV, V and the FNS file were used as activation cross sections. The configurations analysed for the test region were a reference, a beryllium front and a beryllium sandwiched systems in phase IIa, and a reference and a beryllium front with first wall systems in phase IIb. This document describes the results of analysis and comparison between the calculations and the measurements. The prediction accuracy of key parameters in a fusion reactor blanket are examined. The tritium production rates can be well predicted in the reference systems but are fairly underestimated in the system with a beryllium multiplier. Details of experiments and the experimental techniques are described separately in the another report. (author)

Status of RF system for the JAERI energy-recovery linac FEL

International Nuclear Information System (INIS)

Sawamura, Masaru; Nagai, Ryoji

2006-01-01

The two types of the RF sources are used for the JAERI ERL-FEL. One is an all-solid state amplifier and the other is an inductive output tube (IOT). There are advantages of little failure and wide bandwidth for the all-solid state amplifier, low cost and high efficiency for IOT. The property of low cost with the IOT is suitable for a large machine like an energy recovery linac (ERL)

Report of the research results with JAERI's facilities in fiscal 1975

International Nuclear Information System (INIS)

1976-07-01

Results of the research works by educational institutions using facilities of the Japan Atomic Energy Research Institute in fiscal 1975 are reported in individual summaries. Facilities utilized are research reactors, Co-60 irradiation facilities, hot laboratory, Linac and electron accelerators. Fields of research are the following: nuclear physics, radiation damage/solid-state physics, positron annihilation, activation analysis/nuclear chemistry, hot atom chemistry, irradiation effects, biology, and neutron diffraction; and, cooperative works to JAERI. (Mori, K.)

KEK/JAERI joint project on high intensity proton accelerators

International Nuclear Information System (INIS)

Nagamiya, Shoji

2002-01-01

From JFY01, which started on April 1, 2001, a new accelerator project to provide high-intensity proton beams proceeded into a construction phase. This project is conducted under a cooperation of two institutions, KEK and JAERI. The accelerator complex will provide 1 MW proton beams at 3 GeV and 0.75 MW beams at 50 GeV. The project will be completed within six years. In this article I will describe a) the project itself, b) sciences to be pursued at this new accelerator complex and c) the present status and future plans of the project. (author)

KEK/JAERI Joint Project on high-intensity proton accelerators

International Nuclear Information System (INIS)

Nagamiya, Shoji

2003-01-01

From JFY01, which started on April 1, 2001, a new accelerator project to provide high-intensity proton beams proceeded into a construction phase. This project is conducted under a cooperation of two institutions, KEK and JAERI. The accelerator complex will provide 1 MW proton beams at 3 GeV and 0.75 MW beams at 50 GeV. The project will be completed within 6 years. In this article I will describe (a) the project itself, (b) sciences to be pursued at this new accelerator complex and (c) the present status and future plans of the project

Annual report on neutron scattering studies in JAERI, July 1, 1977 - August 31, 1978

International Nuclear Information System (INIS)

Hamaguchi, Yoshikazu; Iizumi, Masashi; Endoh, Yasuo

1978-12-01

Neutron scattering studies carried out by Division of Physics, JAERI, and several universities with neutron beam facilities at JRR-2 and 3 in Tokai are described for the period from July, 1977 to August, 1978. Contents are 51 individual reports and list of publicatios during the period. (author)

A novel approach to the microdosimetry of neutron capture therapy. Part I. High-resolution quantitative autoradiography applied to microdosimetry in neutron capture therapy

International Nuclear Information System (INIS)

Solares, G.R.; Zamenhof, R.G.

1995-01-01

A novel approach to the microdosimetry of neutron capture therapy has been developed using high-resolution quantitative autoradiography (HRQAR) and two-dimensional Monte Carlo simulation. This approach has been applied using actual cell morophology (nuclear and cytoplasmic cell structures) and the measured microdistribution of boron-10 in a transplanted murine brain tumor (GL261) containing p-boronophenylalanine (BPA) as the boron compound. The 2D Monte Carlo transport code for the α and 7 Li charged particles from the 10 B(n,α) 7 Li reactions has been developed as a surrogate to a full 3D approach to calculate a variety of different microdosimetric parameters. The HRQAR method and the surrogate 2D Monte Carlo approach are described in detail and examples of their use are presented. 27 refs., 11 figs., 1 tab

Proceedings of third JAERI-JNC joint conference on nuclear safety research

International Nuclear Information System (INIS)

Anoda, Yoshinari; Oikawa, Tetsukuni; Araya, Fumimasa; Suzuki, Tsugio

2006-03-01

The present report is the proceedings of the third JAERI-JNC joint conference on nuclear safety research held on July 29, 2005 in Tokyo before integration of JAERI and JNC to JAEA. The conference was held for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety research in the new organization. A total of 234 people participated in the conference mainly from the nuclear industries and regulatory organizations. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Suzuki, deputy chairperson of NSC, made a special lecture on recent trends in nuclear safety regulation and expectation for the new organization. Finally, a panel discussion was conducted with the title of 'how to conduct efficiently the nuclear safety research in the new organization' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from JAERI and JNC presented and discussed the subject together with the participants on the floor. Through vigorous exchange of views in the panel discussion and descriptions on the questionnaires, it was obviously expressed that expectation to the safety research of the new

Evaluation of socio-economic effects of R and D results at Japan Atomic Energy Research Institute. 2. Socio-economic evaluation of the basic research at JAERI

International Nuclear Information System (INIS)

2003-11-01

The Japan Atomic Energy Research Institute (JAERI), as a core organization devoted to comprehensive nuclear energy research, has steadily promoted various types of research and development (R and D) studies since its establishment in June 1956. Research activities are aimed at performing (1) R and D for nuclear energy, (2) the utilization and application of radiation-based technologies, and (3) the establishment of basic and fundamental research in the nuclear field. Last year, the socio-economic effects on items (1) and (2) were qualitatively and quantitatively evaluated. The quantitative evaluation of item (3) from the viewpoint of a socio-economic effect, however, calls for a different concept and methodology than previously used cost-benefit approach. Achievements obtained from the activities conducted over the last 10 years implied that socio-economics in basic research funded by the public could contribute to the (1) increase in useful intellectual stocks, (2) upbringing of highly skilled college graduates, (3) construction of new scientific facilities and creation of methodologies, (4) stimulation and promotion of social interrelations by networking, (5) increase of one's ability to solve scientific problems, and (6) establishment of venture companies. In this study, we focused on item (4) for the analysis because it assumed that the external economic effect has a link with the socio-economic effects accompanying the networking formation. For the criteria of socio-economic effects we assume that the external effect becomes significant in proportion to the width of networking and/or the magnitude of cooperation measured by numbers of co-writing studies between JAERI and the research bodies, namely private and governmental sectors and universities. Taking these criteria into consideration, the subsequent four items are prepared for quantitative study. They are (1) to clarify the basic research fields where JAERI has been established a significant effort to

Monte Carlo assessment of boron neutron capture therapy for the treatment of breast cancer

Directory of Open Access Journals (Sweden)

Mundy Daniel W.

2005-01-01

Full Text Available For a large number of women who are diagnosed with breast cancer every year the avail able treatment options are effective, though physically and mentally taxing. This work is a starting point of a study of the efficacy of boron neutron capture therapy as an alternative treatment for HER-2+ breast tumors. Using HER-2-specific monoclonal anti bodies coupled with a boron-rich oligomeric phosphate diester, it may be possible to deliver sufficient amounts of 10B to a tumor of the breast to al low for selective cell destruction via irradiation by thermal neutrons. A comprehensive computational model (MCNP for thermal neutron irradiation of the breast is described, as well as the results of calculations made using this model, in order to determine the optimum boron concentration within the tumor for an effective boron neutron capture therapy treatment, as compared with traditional X-ray radiotherapy. The results indicate that a boron concentration of 50-60 mg per gram of tumor tissue is optimal when considering treatment times, dose distributions and skin sparing. How ever these results are based upon best-guess assumptions that must be experimentally verified.

Dose Determination using alanine detectors in a Mixed Neutron and Gamma Field for Boron Neutron Capture Therapy of Liver Malignancies

DEFF Research Database (Denmark)

Schmitz, T.; Blaickner, M.; Ziegner, M.

2011-01-01

Introduction Boron Neutron Capture Therapy for liver malignancies is being investigated at the University of Mainz. One important aim is the set-up of a reliable dosimetry system. Alanine dosimeters have previously been applied for dosimetry of mixed radiation fields in antiproton therapy, and ma...

Upgrade of a control system for the JAERI ERL-FEL

International Nuclear Information System (INIS)

Kikuzawa, Nobuhiro

2004-01-01

The accelerator control system used for the JAERI ERL-FEL is a PC-based distributed control system that has been in operation since 1992. Since an interface bus of the PCs is obsolete, interface boards for the PCs are difficult to obtain in recent years. Thus we have been developing the CAMAC controller with μITRON operating system to replace the old PCs connected with CAMAC. We will introduce a Java and CORBA environment in the new control system. The control system upgrade, including hardware upgrading and applications rewriting, is described in this paper. (author)

Nominal effective radiation doses delivered during clinical trials of boron neutron capture therapy

International Nuclear Information System (INIS)

Capala, J.; Diaz, A.Z.; Chanana, A.D.

1997-01-01

Boron neutron capture therapy (BNCT) is a binary system that, in theory, should selectively deliver lethal, high linear energy transfer (LET) radiation to tumor cells dispersed within normal tissues. It is based on the nuclear reaction 10-B(n, α)7-Li, which occurs when the stable nucleus of boron-10 captures a thermal neutron. Due to the relatively high cross-section of the 10-B nucleus for thermal neutron capture and short ranges of the products of this reaction, tumor cells in the volume exposed to thermal neutrons and containing sufficiently high concentration of 10-B would receive a much higher radiation dose than the normal cells contained within the exposed volume. Nevertheless, radiation dose deposited in normal tissue by gamma and fast neutron contamination of the neutron beam, as well as neutron capture in nitrogen, 14-N(n,p)14-C, hydrogen, 1-H(n,γ)2-H, and in boron present in blood and normal cells, limits the dose that can be delivered to tumor cells. It is, therefore, imperative for the success of the BNCT the dosed delivered to normal tissues be accurately determined in order to optimize the irradiation geometry and to limit the volume of normal tissue exposed to thermal neutrons. These are the major objectives of BNCT treatment planning

Proceedings of the 2nd JAERI symposium on HTGR technologies October 21 ∼ 23, 1992, Oarai, Japan

International Nuclear Information System (INIS)

1993-01-01

The Japan Atomic Energy Research Institute (JAERI) held the 2nd JAERI Symposium on HTGR Technologies on October 21 to 23, 1992, at Oarai Park Hotel at Oarai-machi, Ibaraki-ken, Japan, with support of International Atomic Energy Agency (IAEA), Science and Technology Agency of Japan and the Atomic Energy Society of Japan on the occasion that the construction of the High Temperature Engineering Test Reactor (HTTR), which is the first high temperature gas-cooled reactor (HTGR) in Japan, is now being proceeded smoothly. In this symposium, the worldwide present status of research and development (R and D) of the HTGRs and the future perspectives of the HTGR development were discussed with 47 papers including 3 invited lectures, focusing on the present status of HTGR projects and perspectives of HTGR Development, Safety, Operation Experience, Fuel and Heat Utilization. A panel discussion was also organized on how the HTGRs can contribute to the preservation of global environment. About 280 participants attended the symposium from Japan, Bangladesh, Germany, France, Indonesia, People's Republic of China, Poland, Russia, Switzerland, United Kingdom, United States of America, Venezuela and the IAEA. This paper was edited as the proceedings of the 2nd JAERI Symposium on HTGR Technologies, collecting the 47 papers presented in the oral and poster sessions along with 11 panel exhibitions on the results of research and development associated to the HTTR. (author)

JAERI TIARA annual report vol. 1 (1992)

International Nuclear Information System (INIS)

Ishigaki, Isao; Nashiyama, Isamu; Naramoto, Hiroshi; Omichi, Hideki; Tanaka, Ryuichi; Watanabe, Hiromasa; Watanabe, Hiroshi

1993-03-01

This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1991 to March 31, 1992, and also gives an outline of the ion accelerators and surrounding apparatus which have been constructed and prepared for various experiments. As well as an outline of the characteristics of AVF cyclotron, 3 MV tandem electrostatic accelerator and other ones, included are 25 summary reports on preparation of experimental apparatus and on the preliminary results of experimental studies using the 3 MV tandem accelerator in the different research fields of beam technology, materials for space environment and nuclear fusion reactor, organic and inorganic functional materials, biology, medicine, radiation chemistry, radioisotope production and nuclear chemistry. Lists of publication, staff of TIARA and cooperated researchers are also given. (author)

JAERI TANDEM and V.D.G. annual report 1992 April 1, 1992 - March 31, 1993

International Nuclear Information System (INIS)

1993-09-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1992 to March 31, 1993. Summary reports of 41 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM and V.D.G. annual report 1994. April 1, 1994 - March 31, 1995

International Nuclear Information System (INIS)

Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Shinohara, Nobuo; Takeuchi, Suehiro; Shoji, Tokio; Okabe, Takashi

1995-10-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1994 to March 31, 1995. Summary reports of 47 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI tandem and V.D.G. annual report 1997. April 1, 1997 - March 31, 1998

International Nuclear Information System (INIS)

Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Sataka, Masao; Nagame, Yuichiro; Takemori, Satoshi; Iwamoto, Akira

1998-10-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1997 to March 31, 1998. Summary reports of 40 papers, and lists of publication, personnel and cooperative researches with universities are contained. (author)

JAERI tandem and V.D.G. annual report 1998. April 1, 1998 - March 31, 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1998 to March 31, 1999. Summary reports of 38 papers, and lists of publication, personnel and cooperative research with universities and contained. (author)

JAERI tandem and V.D.G. annual report 1993. April 1, 1993 - March 31, 1994

International Nuclear Information System (INIS)

Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Kazumata, Yukio; Shinohara, Nobuo; Takeuchi, Suehiro; Okabe, Takashi

1994-11-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1993 to March 31, 1994. Summary reports of 43 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM and V.D.G. annual report 1995. April 1, 1995 - March 31, 1996

Energy Technology Data Exchange (ETDEWEB)

Takeuchi, Suehiro; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Nagame, Yuichiro; Shoji, Tokio; Okabe, Takashi; Maekawa, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

1996-08-01

This annual report describes research activities which have been performed with the JAERI Tandem accelerator and the Van de Graaff accelerator from April 1, 1995 to March 31, 1996. Summary reports of 59 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM and V.D.G. annual report 1996. April 1, 1996 - March 31, 1997

International Nuclear Information System (INIS)

Takeuchi, Suehiro; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Nagame, Yuichiro; Shoji, Tokio; Okabe, Takashi; Maekawa, Hiroshi

1997-09-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaf accelerator from April 1, 1996 to March 31, 1997. Summary reports of 48 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM and V.D.G. annual report 1994. April 1, 1994 - March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Shinohara, Nobuo; Takeuchi, Suehiro; Shoji, Tokio; Okabe, Takashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

1995-10-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1994 to March 31, 1995. Summary reports of 47 papers, and list of publications, personnel and cooperative researches with universities are contained. (author).

Physical engineering and medical physics on boron neutron capture therapy

International Nuclear Information System (INIS)

Sakurai, Yoshinori

2011-01-01

The contents of physical engineering and medical physics that support boron neutron capture therapy (BNCT) can be roughly classified to the four items, (1) neutron irradiation system, (2) development and improvement of dose assessment techniques, (3) development and improvement of dose planning system, and (4) quality assurance and quality control. This paper introduces the BNCT at Kyoto University Research Reactor Institute, with a focus on the basic physics of BNCT, thermal neutron irradiation and epithermal neutron irradiation, heavy water neutron irradiation facilities of KUR, and medical irradiation system of KUR. It also introduces the world's first BNCT clinical cyclotron irradiation system (C-BENS) of Kyoto University Research Reactor Institute, BNCT dose assessment techniques, dose planning system, and quality assurance and quality control. (A.O.)

Radioactive waste generated from JAERI partitioning-transmutation cycle system

Energy Technology Data Exchange (ETDEWEB)

Shinichi, Nakayama; Yasuji, Morita; Kenji, Nishihara [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

2001-07-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI processes. Long-lived radionuclides such as {sup 14}C and {sup 59}Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (author)

Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

International Nuclear Information System (INIS)

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

2003-01-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

Off-line tests of superconducting resonators of the JAERI tandem booster

International Nuclear Information System (INIS)

Shibata, Michihiro; Ishii, Tetsuro; Takeuchi, Suehiro

1993-01-01

The JAERI tandem booster linac, which consists of 46 superconducting quarter wave resonators, is under construction. Off-line tests for resonators were performed. Accelerating field levels of 7MV/m were obtained at an rf input of 4W with most resonators. A maximum field level of 12.7MV/m was obtained. The Q-value was degraded when resonators were cooled down slowly around a temperature of 120K. We investigated this phenomenon by changing the cooling rate. (author)

JAERI 10kW High Power ERL-FEL and Its Applications in Nuclear Energy Industries

CERN Document Server

Minehara, E J; Iijima, H; Kikuzawa, N; Nagai, R; Nishimori, N; Nishitani, T; Sawamura, M; Yamauchi, T

2005-01-01

The JAERI high power ERL-FEL has been extended to the more powerful and efficient free-electron laser (FEL) than 10kW for nuclear energy industries, and other heavy industries like defense, shipbuilding, chemical industries, environmental sciences, space-debris, and power beaming and so on. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, we need the efficient and powerful FEL driven by the JAERI compact, stand-alone and zero boil-off super-conducting RF linac with an energy-recovery geometry. Our discussions on the ERL-FEL will cover the current status of the 10kW upgrading and its applications of non-thermal peeling, cutting, and drilling to decommission the nuclear power plants, and to demonstrate successfully the proof of principle prevention of cold-worked stress-corrosion cracking failures in nuclear power reactors under routine operation using small cubic low-Carbon stainless steel samples.

Manpower development and international cooperation in Nuclear Technology and Education Center, JAERI

International Nuclear Information System (INIS)

Shiba, Koreyuki; Tojo, Takao; Takada, Kazuo; Nomura, Masayuki

1996-01-01

Nuclear Technology and Education Center was founded in 1958 and now has two branches, Tokyo Education Center at Bunkyo-ku, Tokyo and Tokai Education Center at Tokai, Ibaraki-ken. The objective was to educate and train nuclear engineers and scientists for implementing the nation's program of atomic energy research, development and utilization. A variety of training courses have been prepared and carried out to meet the requirements of the nuclear community. In recent years, activities of getting the public acceptance have become important for nuclear energy deployment in Japan. Many short courses have been implemented at JAERI sites and cities for providing the public including high school teachers with basic knowledge on nuclear energy. International training programs of the center were started with the cooperation of the Japan International Cooperation Agency (JICA) in 1985 and of the International Atomic Energy Agency (IAEA) in 1987. International seminars were implemented for improving nuclear safety by inviting participants from the former Soviet Union, central/east European countries and the neighboring countries of Japan under the direction of the Science and Technology Agency (STA) in 1992. STA and JAERI are starting new programs of helping Asian and Pacific countries to develop nuclear manpower. (author)

General activities of JAERI nuclear data center and Japanese nuclear data committee

International Nuclear Information System (INIS)

Fukahori, Tokio

1999-01-01

The nuclear data center of Japan Atomic Energy Research Institute (JAERI/NDC) is playing the role of Japanese domestic nuclear data center and gateway to foreign data centers. As the domestic nuclear data center, activities of JAERI/NDC are 1) compiling the Japanese Evaluated Nuclear Data Library (JENDL) for both general and special purposes, 2) importing and exporting nuclear data, 3) nuclear data services for the domestic users, and 4) organizing japanese Nuclear Data Committee (JNDC) as a secretariat. Compiled JENDL General Purpose Files up to now are JENDL-1, 2, 3, 3.1 and 3.2. The data for 340 nuclei in the energy range from 10 -5 eV to 20 MeV are available in JENDL-3.2. JENDL Special Purpose Files were also prepared in order to meet the requests from the specified application fields. JNDC has about 140 members. JNDC consists of Main Committee, Steering Committee, Subcommittee on Nuclear Data, Subcommittee on Reactor Constants, Subcommittee on Nuclear Fuel Cycle and Standing Groups. Above subcommittees are performing essential evaluation for the files described above, checking the JENDL files through the benchmark and integral testing as well as considering the standard group constant, and considering about evaluation of decay heat and nuclide generation/depletion and fission product yields. (author)

Development of an integrated system for nuclear material accountancy and control at JAERI

International Nuclear Information System (INIS)

Nishimura, Hideo; Nishizawa, Satoshi

1993-01-01

This paper describes the design concept and the current status of an integrated system for nuclear material accountancy and control, which is under development at JAERI. We, at JAERI, have decided to update the current system for material accountancy and control and to develop the integrated new system with a consolidated data base in order to augment transparency, credibility and promptness of the system, to materialize a prudent control of obligations required by bilateral nuclear cooperation agreements, and to give information for the physical protection, safely handling, property control and cost-effective use of nuclear material and for public relations. The system is composed of two work-stations operated by UNIX, one for implementation and the other for development, and many terminals located at the headquarters, administrative offices, and research facilities and laboratories. It is connected with a mainframe computer. There are many files on the data base to record inventory changes, book and physical inventories, and statistics on material balances. These files are controlled by a commercial data base management system which enables us to make access to data on the files with a simple query language, spread sheet type software or an application program. (author)

Development of a distributed control system for the JAERI tandem accelerator facility

International Nuclear Information System (INIS)

Hanashima, Susumu

2005-01-01

In the JAERI tandem accelerator facility, we are building accelerator complex aiming generation and acceleration of radio nuclear beam. Several accelerators, ion sources and a charge breeder are installed in the facility. We are developing a distributed control system enabling smooth operation of the facility. We report basic concepts of the control system in this article. We also describe about a control hardware using plastic optical fiber, which is developed for the control system. (author)

Boron thermal/epithermal neutron capture therapy

International Nuclear Information System (INIS)

Fairchild, R.G.

1982-01-01

The development of various particle beams for radiotherapy represents an attempt to improve dose distribution, and to provide high LET radiations which are less sensitive to ambient physical and radiobiological factors such as oxygen tension, cell cycle, and dose rate. In general, a compromise is necessary as effective RBE is reduced in order to spread the dose distribution over the anticipated tumor volume. The approach of delivering stable non-toxic isotopes to tumor, and then activating these atoms subsequently via an external radiation beam has mator advantages; problems associated with high uptake of these isotopes in competing cell pools are obviated, and the general tumor volume can be included in the treatment field of the activating beam. As long as the normal tissues supporting tumor show a low uptake of the isotope to be activated, and as long as the range of the reaction products is short, dose will be restricted to tumor, with a consequent high therapeutic ratio. Neutron Capture Therapy (NCT) is generally carried out by activating boron-10 with low energy neutrons. The range of the high LET, low OER particles from the 10 B(n, α) 7 Li reaction is approx. 10μ, or one cell diameter, a situation that is optimal for cell killing. Significant advantages may be gained by using the NCT procedure in conjunction with improved tissue penetration provided with epithermal or filtered beams, and new compounds showing physiological binding to tumor

Boron neutron capture therapy induces apoptosis of glioma cells through Bcl-2/Bax

OpenAIRE

Wang, Peng; Zhen, Haining; Jiang, Xinbiao; Zhang, Wei; Cheng, Xin; Guo, Geng; Mao, Xinggang; Zhang, Xiang

2010-01-01

Abstract Background Boron neutron capture therapy (BNCT) is an alternative treatment modality for patients with glioma. The aim of this study was to determine whether induction of apoptosis contributes to the main therapeutic efficacy of BNCT and to compare the relative biological effect (RBE) of BNCT, γ-ray and reactor neutron irradiation. Methods The neutron beam was obtained from the Xi'an Pulsed Reactor (XAPR) and γ-rays were obtained from [60Co] γ source of the Fourth Military Medical Un...

New compounds for neutron capture therapy (NCT) and their significance

International Nuclear Information System (INIS)

Fairchild, R.G.; Bond, V.P.

1982-01-01

Clearly the most effective tumor therapy would be obtained by the selective targeting of cytotoxic agents to tumor cells. Although many biomolecules are known to be taken up in tumors, the targeting of cytotoxic agents to tumors is limited by the fact that other essential cell pools compete with equal or even greater effectiveness. The approach of delivering stable non-toxic isotopes to tumor, with activation by means of an external radiation beam, is advantageous for two reasons: (1) it obviates problems associated with high uptake of isotopes in normal tissues, as these cell pools can be excluded from the radiation field, and (2) the general tumor area can be included in the activating beam field; thus, the possibility exists that all microscopic tumor extensions can be irradiated. As long as range of reaction products is short, dose will be restricted to the tumor, with a resultant high therapeutic ratio. This method can be accomplished with either photon activation therapy (PAT) or Neutron Capture Therapy (NCT), the latter will be emphasized here. The range of the high LET, low OER particles from the 10 B(n,α) 7 Li reaction is approx. 10 μm, or one cell diameter; hence this reaction is optimal for cell killing. A number of biomolecules have been investigated as possible vehicles for transport of boron to tumors, including phenothiazines, thiouracils, porphyrins, nucleosides, and amino acids. Biodistributions of these compounds show selective concentration in tumor adequate for therapy. The biological halflives are in the order of days, allowing the possibility of fractionated or protracted irradiations. The radiobiological and physical implication of these parameters on NCT are discussed. The possibility of using an approximately-monoenergetic, scandium-filtered beam of about 2 keV, to reduce the dose from background radiations by about 85%, is also discussed

Boron-containing thioureas for neutron capture therapy

International Nuclear Information System (INIS)

Ketz, H.

1993-01-01

Melanin is produced in large amounts in malignant melanotic melanomas. Because thiourea compounds are covalently incorporated into melanin during its biosynthesis, the preparation of boronated thiourea-derivatives is of particular interest for the BNCT (Boron Neutron Capture Therapy). Accumulation of boron in tumors by means of boronated thiourea-derivatives may therefore provide levels of 10 B which are useful for BNCT. In BNCT the tumor containing the boron compound is irradiated with epithermal neutrons to generate He- and Li-nuclei from the 10 B which can then destroy the tumor cells. Because of the short ranges of these particles (approximately one cell diameter) the damage will be almost exclusively confined to the tumor leaving normal tissue unharmed. High accumulation of 2-mercapto-1-methylimidazole (methimazole) in melanotic melanomas has been described in the literature. Boronated derivatives of methimazole were therefore synthesized. Boron was in the form of a boronic acid, a nido-carbonate and a mercaptoundeca hydro-closo-dodecaborate (BSH). The synthesis of the boron cluster derivatives of methimazole (nido-carborate- and BSH-derivatives) with 9 resp. 12 boron atoms in the molecule were expected to achieve higher concentrations of boron in the tumor than in the case of the boronic acid compound with its single boron atom. (orig.) [de

Single photon image from PET with insertable collimator for boron neutron capture therapy

International Nuclear Information System (INIS)

Jung, Jooyoung; Suh, Tae Suk; Hong, Key Jo

2014-01-01

Boron neutron capture therapy (BNCT) is a radiation therapy technique for treating deep-seated brain tumors by irradiation with a thermal neutron in which boron-labelled low molecular weight compounds. Once completed, a single photon emission computed tomography (SPECT) scan is conducted to investigate for the region of therapy using an isotope exclusive to SPECT. In the case of an existing PET/SPECT combination system, at least two types of isotopes should be used for each scan with their purposes. Recently, researchers examined the effects of PET/SPECT dual modality on animal imaging systems. They reported that the PET/SPECT combination system was effective for simultaneous achievement of a single event and coincidence. The aim of our proposed system is to confirm the feasibility of extraction of two types of images from one PET module with an insertable collimator for brain tumor treatment during the BNCT. We attempted to acquire the PET and SPECT images simultaneously using only PET without an additional isotope. Single photon images were acquired using an insertable collimator on a PET detector

Improvement of JCDS, a computational dosimetry system in JAEA for neutron capture therapy

International Nuclear Information System (INIS)

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Matsumura, Akira; Yamamoto, Tetsuya; Nakagawa, Yoshinobu; Kageji, Teruyoshi

2006-01-01

JCDS, a computational dosimetry system for neutron capture therapy, was developed by Japan Atomic Energy Agency. The system has been sophisticated to facilitate dose planning so far. In dosimetry with JCDS for BNCT clinical trials at JRR-4, several absorbed doses and the dose distributions are determined by a voxel model consisted of 2x2x2mm 3 voxel cells. By using the detailed voxel model, accuracy of the dosimetry can be improved. Clinical trials for melanoma and head-and-neck cancer as well as brain tumor were started using hot version of JCDS in 2005. JCDS is also being of improved so as to enable a JCDS application to dosimetry by PHITS as well as dosimetry by MCNP. By using PHITS, total doses of a patient by a combined modality therapy, for example a combination of BNCT and proton therapy, can be estimated consistently. Moreover, PET images can be adopted in combination with CT and MRI images as a farsighted approach. JCDS became able to identify target regions by using the PET values. (author)

A comparison of the COG and MCNP codes in computational neutron capture therapy modeling, Part II: gadolinium neutron capture therapy models and therapeutic effects.

Science.gov (United States)

Wangerin, K; Culbertson, C N; Jevremovic, T

2005-08-01

The goal of this study was to evaluate the COG Monte Carlo radiation transport code, developed and tested by Lawrence Livermore National Laboratory, for gadolinium neutron capture therapy (GdNCT) related modeling. The validity of COG NCT model has been established for this model, and here the calculation was extended to analyze the effect of various gadolinium concentrations on dose distribution and cell-kill effect of the GdNCT modality and to determine the optimum therapeutic conditions for treating brain cancers. The computational results were compared with the widely used MCNP code. The differences between the COG and MCNP predictions were generally small and suggest that the COG code can be applied to similar research problems in NCT. Results for this study also showed that a concentration of 100 ppm gadolinium in the tumor was most beneficial when using an epithermal neutron beam.

The JAERI-KEK joint project on high intensity proton accelerator and overview of nuclear transmutation experimental facilities

International Nuclear Information System (INIS)

Ikeda, Yujiro

2001-01-01

A status of the JAERI/KEK joint project on High Intensity Proton Accelerator is overviewed. It is highlighted that Experimental facilities for development of the accelerator driven system (ADS) for nuclear transmutation technology is proposed under the project. (author)

Neutron spectrum for neutron capture therapy in boron; Espectro de neutrones para terapia por captura de neutrones en boro

Energy Technology Data Exchange (ETDEWEB)

Medina C, D.; Soto B, T. G. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Programa de Doctorado en Ciencias Basicas, 98068 Zacatecas, Zac. (Mexico); Baltazar R, A. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Programa de Doctorado en Ingenieria y Tecnologia Aplicada, 98068 Zacatecas, Zac. (Mexico); Vega C, H. R., E-mail: dmedina_c@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico)

2016-10-15

Glioblastoma multiforme is the most common and aggressive of brain tumors and is difficult to treat by surgery, chemotherapy or conventional radiation therapy. One treatment alternative is the Neutron Capture Therapy in Boron, which requires a beam modulated in neutron energy and a drug with {sup 10}B able to be fixed in the tumor. When the patients head is exposed to the neutron beam, they are captured by the {sup 10}B and produce a nucleus of {sup 7}Li and an alpha particle whose energy is deposited in the cancer cells causing it to be destroyed without damaging the normal tissue. One of the problems associated with this therapy is to have an epithermal neutrons flux of the order of 10{sup 9} n/cm{sup 2}-sec, whereby irradiation channels of a nuclear research reactor are used. In this work using Monte Carlo methods, the neutron spectra obtained in the radial irradiation channel of the TRIGA Mark III reactor are calculated when inserting filters whose position and thickness have been modified. From the arrangements studied, we found that the Fe-Cd-Al-Cd polyethylene filter yielded a ratio between thermal and epithermal neutron fluxes of 0.006 that exceeded the recommended value (<0.05), and the dose due to the capture gamma rays is lower than the dose obtained with the other arrangements studied. (Author)

Heat treatment of long pulse operation for the JAERI ERL-FEL

International Nuclear Information System (INIS)

Sawamura, Masaru; Nagai, Ryoji; Kikuzawa, Nobuhiro; Hajima, Ryoichi; Minehara, Eisuke

2005-01-01

RF power sources are replaced from all-solid-state amplifiers to IOT amplifiers for the superconducting accelerators (SCAs) and a vacuum tube amplifier for the SHB of the JAERI ERL-FEL. A long pulse operation increased the pressure in the cryostat of the SCA. The single-cell SCA can be operated in 9% duty according to the time constant of the pressure decay in the cryostat. SHB can be operated in 4% duty which is limited by the frequency range of the tuners. The result of the ABAQUS calculation shows the more duty operation. (author)

Long-term nuclear knowledge management (NKM) of innovative nuclear energy systems (INES). A case study of the Japan Atomic Energy Research Institute (JAERI)

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki; Bezdek, Roger H.; Sawada, Tetsuo

2008-01-01

Within JAERI, funds invested in a 45-year study of LWR totaled 4.2b$ for research and 3.4b$ (34,718 man years) for personnel. The benefits to taxpayers from this JAERI work were estimated to be about 6.3b$ , resulting in a favorable cost-benefit ratio of 1.5 (6.3/4.2). JAERI is a national research institute and this figure may be regarded as sufficiently high, and many high risk and complex tasks were completed successfully. Funds invested in the 32-year study of HTGR were 1.5b$ for R and D and 0.3b$ (2966 man years) for personnel. Commercialized HTGR will result in a cost reduction of electricity during power generation. Retail cost is 0.36b$/year and the share of JAERI (MCP) is 0.018b$/year. Funds invested in the 32-year study of FR were 5.4b$ for R and D and 0.6b$ (6331 man years) for personnel. Estimate is that after commercialization in 2050, a FR will generate revenue from electricity as high as 1687b$ during the period 2050-2100, or 34b$/year - which is greater than that of LWR. However, there is substantial uncertainty in these estimates. To achieve long-term INES, it is necessary to develop the sustainable scenarios and the long-term robust NKM, as shown in the present study. (author)

Radiobiology of boron neutron capture therapy

International Nuclear Information System (INIS)

Bond, V.P.

1986-01-01

The author addresses the question of single session versus protracted therapy in the application of boron neutron therapy to tumors. As background he discusses the reasoning behind the current use of fractionated therapy with conventional low-LET radiations and difference which may obtain for neutron therapy. Several aspects of dose rates and dose levels are then addressed

Report to the 238U discrepancy task force on SIOB fits to the ORNL, CBNM, and JAERI transmission data

International Nuclear Information System (INIS)

Olsen, D.K.

1984-05-01

The computer code SIOB has been used to obtain least-squares simultaneous-sample shape fits to the recent 238 U transmission data of ORNL, CBNM, and JAERI over the energy regions 1460 to 1820 eV, 2470 to 2740 eV, and 3820 to 4000 eV. The fits indicate that much of the systematic discrepancy in the published neutron widths from these data arose in the data analysis procedure. Except for the 3820- to 4000-eV JAERI data, the systematic differences in the resulting neutron widths from the present widths are larger than those contained in any existing evaluation. These fits were performed as part of the work for the NEANDC ad hoc 238 U Discrepancy Task Force. 20 references

JAERI TANDEM annual report 2003. April 1, 2003 - March 31, 2004

International Nuclear Information System (INIS)

Ishii, Tetsuro; Takeuchi, Suehiro; Oshima, Masumi; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

2004-12-01

This annual report describes research activities, which have been performed with the JAERI tandem accelerator and its energy booster from April 1, 2003 to March 31, 2004. Summary reports of 42 papers, and lists of publication, personnel and cooperative research with universities are contained. The following are some of the highlights in FY 2003. The JAERI-KEK joint project of developing an ISOL-based radioactive-nuclear beam facility has been running since FY2001. In FY2003, the accelerators (split-coaxial RFQ, IH linac) in KEK were moved to a remodeled room in the tandem accelerator facility. The ion source in the ISOL was developed for the use of a UC 2 target. The ISOL was connected to an ECR charge breeder operating at 18 GHz. An ECR ion source for stable-nuclear beams was also installed. This facility accelerates heavy-ions with A/q 47 K was carried out by deep-inelastic collisions with a 48 Ca beam. The electromagnetic properties of low-lying states in 66,68Z n, 78 Se isotopes were determined by projectile Coulomb excitation. High-spin states in 169,172,187 Re, 145,146 Tb and 179 Au, and a high-spin isomer of 136 Ba were identified by the γ-ray detector array, GEMINI-II. In one of the heaviest nuclei 257 No, the spin-parity of its ground state was determined by α-decay spectroscopy using the ISOL and a He gas-jet system. In research of nuclear reactions, fusion cross sections of 64 Ni + 154 Sm and 86 Kr + 134,138 Ba reactions were measured by using the recoil mass separator JAERI-RMS in order to investigate the dependence of sub-barrier fusion on the nuclear deformation and shell structure. The exclusive cross section of 8 Li (α, n) reaction was measured with high statistics in the energy region, E cm = 0.9-2.8 MeV, of astrophysical interest by using a highly pure low-energy beam of unstable 8 Li nuclei from the JAERI-RMS. In research of nuclear chemistry, fluoride complexation of element 104, rutherfordium (Rf), produced in the 248 Cm ( 18 O, 5n) 261 Rf

A new target concept for proton accelerator driven boron neutron capture therapy applications

International Nuclear Information System (INIS)

Powell, J.R.; Ludewig, H.; Todosow, M.; Reich, M.

1998-01-01

A new target concept termed Discs Incorporating Sector Configured Orbiting Sources (DISCOS), is proposed for spallation applications, including BNCT (Boron Neutron Capture Therapy). In the BNCT application a proton beam impacts a sequence of ultra thin lithium DISCOS targets to generate neutrons by the 7 Li(p,n) 7 Be reaction. The proton beam loses only a few keV of its ∼MeV energy as it passes through a given target, and is re-accelerated to its initial energy, by a DC electric field between the targets

Historical evolution of nuclear energy systems development and related activities in JAERI. Fission, fusion, accelerator utilization

Energy Technology Data Exchange (ETDEWEB)

Tone, Tatsuzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

Overview of the historical evolution of nuclear energy systems development and related activities in JAERI is given in the report. This report reviews the research and development for light water reactor, fast breeder reactor, high temperature gas reactor, fusion reactor and utilization of accelerator-based neutron source. (author)

Technical development of high intensity proton accelerators in Japan Atomic Energy Research Institute (JAERI)

International Nuclear Information System (INIS)

Mizumoto, Motoharu

1995-01-01

Science and Technology Agency decided 'Options making extra gains of actinides and fission products (OMEGA)' and to promote the related researches. Also in JAERI, the research on the group separation method for separating transuranic elements, strontium and cesium from high level radioactive wastes has been carried out since the beginning of 1970s. Also the concept of the fast reactors using minor actinide mixture fuel is being established, and the accelerator annihilation treatment utilizing the nuclear spallation reaction by high energy protons has been examined. In this report, from the viewpoint of the application of accelerators to atomic energy field, the annihilation treatment method by the nuclear spallation reaction utilizing high intensity proton accelerators, the plan of the various engineering utilization of proton beam, and the development of accelerators in JAERI are described. The way of thinking on the annihilation treatment of radioactive waste, the system using fast neutrons, the way of thinking on the development of high intensity proton accelerator technology, the steps of the development, the research and development for constructing the basic technology accelerator, 2 MeV beam acceleration test, the basic technology accelerator utilization facility and so on are reported. (K.I.)

Proceedings of workshop on 'boron chemistry and boron neutron capture therapy'

International Nuclear Information System (INIS)

Kitaoka, Yoshinori

1993-09-01

This volume contains the proceedings of the 5th Workshop on 'the Boron Chemistry and Boron Neutron Capture Therapy' held on February 22 in 1993. The solubility of the boron carrier play an important role in the BNCT. New water-soluble p-boronophenylalanine derivatives are synthesized and their biological activities are investigated (Chap. 2 and 3). Some chemical problems on the BNCT were discussed, and the complex formation reaction of hydroxylboryl compounds were studied by the paper electrophoresis (Chap. 4). The results of the medical investigation on the BNCT using BSH compounds are shown in Chap. 5. Syntheses of o- and m-boronophenylalanine were done and their optical resolution was tried (Chap. 6). The complex formation reaction of p-boronophenylalanine (BPA) with L-DOPA and the oxidation reaction of the analogs are found in Chap. 7. The pka of BPA were determined by the isotachophoresis (Chap. 8). The chemical nature of dihydroxyboryl compounds were investigated by an infrared spectroscopy and electrophoresis (Chap. 9). New synthetic methods of BPA and p-boronophenylserine using ester of isocyanoacetic acid are described in Chap. 10. The induction of chromosomal aberations by neutron capture reaction are discussed from a point of the biological view. The a of the presented papers are indexed individually. (J.P.N.)

Boron neutron capture therapy combined with fractionated photon irradiation for glioblastoma: A recursive partitioning analysis of BNCT patients

International Nuclear Information System (INIS)

Nakai, K.; Yamamoto, T.; Aiyama, H.; Takada, T.; Yoshida, F.; Kageji, T.; Kumada, H.; Isobe, T.; Endo, K.; Matsuda, M.; Tsurubuchi, T.; Shibata, Y.; Takano, S.; Mizumoto, M.; Tsuboi, K.; Matsumura, A.

2011-01-01

Eight patients to received Boron Neutron Capture Therapy (BNCT) were selected from 33 newly diagnosed glioblastoma patients (NCT(+) group). Serial 42 glioblastoma patients (NCT(−) group) were treated without BNCT. The median OS of the NCT(+) group and NCT (−) group were 24.4 months and 14.9 months. In the high risk patients (RPA class V), the median OS of the NCT(+) group tended to be better than that of NCT(−) group. 50% of BNCT patients were RPA class V. - Highlights: ► We treated 8 patients with boron neutron capture therapy (NCT) for glioblastoma. ► We compare the overall survival between NCT including series and without NCT series. ► The median overall survival of the NCT including series was 24.4 months. ► In the high risk patients, the median OS of NCT including series tended to be better.

Recent activity on the post-irradiation analyses of nuclear fuels and actinide samples at JAERI

International Nuclear Information System (INIS)

Shinohara, Nobuo; Nakahara, Yoshinori; Kohno, Nobuaki; Tsujimoto, Kazufumi

2003-01-01

Radiochemical analyses of spent fuels have been carried out at JAERI for contributing to the development of nuclear technologies, where several samples from research reactors and nuclear power plants were analyzed to obtain isotopic compositions and burnups. The history and procedures of the radiochemical analyses are depicted and some recent results are given in this paper. (author)

A review of JAERI R and D activities on the negative-ion-based neutral beam injection system

International Nuclear Information System (INIS)

Ohara, Yoshihiro; Akiba, Masato; Araki, Masanori

1990-08-01

R and D efforts to realize a negative-ion-based neutral beam injection system have been made intensively at JAERI for the past several years. Concerning a high current negative ion source which is one of the most important R and D items, a 10 A, 50 keV negative hydrogen ion beam has been produced successfully. The negative ion beam current and the current density correspond already to the value required for the negative-ion-based NBI system. In order to increase the beam energy further, a 350 keV, 0.1 A test stand has been constructed, and the test of a high energy negative ion accelerator has started. Concerning a high energy acceleration power supply, an inverter type power supply which has a high speed AC switch was proposed and applied to the 100 kV, 5 A power supply for JAERI Electron Beam Irradiation Stand. The reliable operation indicates that the concept of this system can be applied for a MV class acceleration power supply. As one of the promising candidates for a beam dump cooling element, an externally-finned swirl tube was proposed and tested to have a high burnout heat flux of 4.1 kW/cm 2 , which is high enough for the next NBI system. The R and Ds on the negative-ion-based NBI system have made great progress at JAERI in recent years. The construction of a 500 keV class NBI system has become realistic from the engineering point of view. (author)

Design study of a medical reactor for Boron Neutron Capture Therapy

International Nuclear Information System (INIS)

Sasaki, M.; Hirota, J.; Tamao, S.; Kanda, K.; Mishima, Y.

1992-01-01

A new design study of a medical reactor for Boron Neutron Capture Therapy (BNCT) has been carried out. The reactor is to be used exclusively for the treatment of malignant melanoma and other cancers as well as for the further biomedical research. Main specifications of the reactor are as follows; thermal power of 2 MW, water cooling by natural convection, semitight core of triangular lattice, UO 2 fuel rod of 9.5 mm diameter and no refueling in the reactor-life. Three horizontal and one vertical neutron beam hole are to be provided to deliver thermal and epithermal neutrons. N-γ coupling Sn transport calculations indicate that the patient treatment period will be about 30 minutes with minimal fast neutron and gamma contaminants. (author)

Boron neutron capture therapy for malignant brain tumor and future potential

International Nuclear Information System (INIS)

Nakagawa, Yoshinobu; Hatanaka, Hiroshi.

1994-01-01

This paper presents therapeutic experience with boron neutron capture therapy (BNCT) for malignant brain tumors. Nine patients who survived for 10 years or more as of 1986 are given in a table. A review of the 9 patients concluded that physical dose of 15 Gy is required. In addition, the following factors are defined to be the most important: (1) to determine tumor size and depth as accurately as possible, (2) to measure neutron doses in the deepest site of the tumor during irradiation, (3) to measure the content of boron within the tumor, and to deliver neutron beams as deeply as possible. Finally, the importance of knowing RBE of alpha particles for tumor cells of the human brain is emphasized. (N.K.)

JAERI TANDEM, LINAC and V.D.G. annual report 1990. April 1, 1990 - March 31, 1991

International Nuclear Information System (INIS)

1991-10-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1990 to March 31, 1990. Summary reports of 38 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

JAERI TANDEM, LINAC and V.D.G. annual report 1991 April 1, 1991 - March 31, 1992

International Nuclear Information System (INIS)

1992-09-01

This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1991 to March 31, 1992. Summary reports of 44 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

Study on burnup credit evaluation method at JAERI towards securing criticality safety rationale for management of spent fuel

International Nuclear Information System (INIS)

Nomura, Y.

1998-01-01

Lately, due to massive accumulation of spent fuel discharged from light water reactors in Japan, it is gradually demanded to introduce the so-called burnup credit methodology into criticality safety design for nuclear fuel cycle facilities, such as spent fuel storage pools and transport casks. In order to save space in the spent fuel storage pool of the Rokkasho Reprocessing Plant, the burnup credit design has been firstly implemented for its criticality safety evaluation. Here, its design conditions and operational control procedures are briefly shown and research using burned fuel at JAERI is explained to support its licensing safety review, focusing on the relevant content of the Nuclear Criticality Safety Handbook of Japan, which has been prepared so far and planned in the near future. Finally, international co-operation for study on burnup credit issues practiced by JAERI is addressed. (author)

Development of web database system for JAERI ERL-FEL

International Nuclear Information System (INIS)

Kikuzawa, Nobuhiro

2005-01-01

The accelerator control system for the JAERI ERL-FEL is a PC-based distributed control system. The accelerator status record is stored automatically through the control system to analyze the influence on the electron beam. In order to handle effectively a large number of stored data, it is necessary that the required data can be searched and visualized in easy operation. For this reason, a web database (DB) system which can search of the required data and display visually on a web browser was developed by using open source software. With introduction of this system, accelerator operators can monitor real-time information anytime, anywhere through a web browser. Development of the web DB system is described in this paper. (author)

Development of web database system for JAERI ERL-FEL

Energy Technology Data Exchange (ETDEWEB)

Kikuzawa, Nobuhiro [Japan Atomic Energy Research Inst., Kansai Research Establishment, Advanced Photon Research Center, Tokai, Ibaraki (Japan)

2005-06-01

The accelerator control system for the JAERI ERL-FEL is a PC-based distributed control system. The accelerator status record is stored automatically through the control system to analyze the influence on the electron beam. In order to handle effectively a large number of stored data, it is necessary that the required data can be searched and visualized in easy operation. For this reason, a web database (DB) system which can search of the required data and display visually on a web browser was developed by using open source software. With introduction of this system, accelerator operators can monitor real-time information anytime, anywhere through a web browser. Development of the web DB system is described in this paper. (author)

Computational Dosimetry and Treatment Planning Considerations for Neutron Capture Therapy

International Nuclear Information System (INIS)

Nigg, David Waler

2003-01-01

Specialized treatment planning software systems are generally required for neutron capture therapy (NCT) research and clinical applications. The standard simplifying approximations that work well for treatment planning computations in the case of many other modalities are usually not appropriate for application to neutron transport. One generally must obtain an explicit three-dimensional numerical solution of the governing transport equation, with energy-dependent neutron scattering completely taken into account. Treatment planning systems that have been successfully introduced for NCT applications over the past 15 years rely on the Monte Carlo stochastic simulation method for the necessary computations, primarily because of the geometric complexity of human anatomy. However, historically, there has also been interest in the application of deterministic methods, and there have been some practical developments in this area. Most recently, interest has turned toward the creation of treatment planning software that is not limited to any specific therapy modality, with NCT as only one of several applications. A key issue with NCT treatment planning has to do with boron quantification, and whether improved information concerning the spatial biodistribution of boron can be effectively used to improve the treatment planning process. Validation and benchmarking of computations for NCT are also of current developmental interest. Various institutions have their own procedures, but standard validation models are not yet in wide use

Development of authentication system for the fast critical assembly (FCA) portal monitor (P/M) and penetration monitor (PN/M) systems of JAERI

International Nuclear Information System (INIS)

Ogawa, Hironobu; Mukaiyama, Takehiko

1999-05-01

The advanced comprehensive containment and surveillance system for the Fast Critical Assembly facility (FCA) of the Japan Atomic Energy Research Institute (JAERI) consists of a Portal monitor (P/M) and a Penetration Monitor (PN/M) systems. The development of these systems was completed in 1988 for alleviating the burdens of manpower and radiation problems in the frequent NDA inspections. After the completion of the field trial test (Phase III), in 1990, the International Atomic Energy Agency (IAEA) accepted the system on condition that an independent IAEA authentication equipment would be provided. The development of the authentication measures was carried out jointly by both the Japan Support Programme for Agency Safeguards (JASPAS) and the U.S. Program of Technical Assistance to IAEA Safeguards (POTAS), and also under the research agreement for the safeguards research and development between JAERI and the US Department of Energy (USDOE). The concept and design requirements of the authentication system were developed by IAEA, but the design and development of the authentication equipment were jointly funded both by JASPAS and POTAS, and also the fund of JAERI was provided for the Sandia National Laboratories (SNL) through USDOE. SNL developed and constructed the authentication system in two phase as Phase I and Phase II. JAERI financed the development of the Phase I and Phase II hardware and software, and the installation of the authentication equipment at the FCA facility, and also carried out the modification of the circuitry and devices for both the P/M and the PN/M systems as well as the reconstruction of the PN/M Junction Unit for compatibility with the implementation of the authentication measures. After the completion of consecutive field trial test of the P/M, the PN/M and the authentication system, IAEA accepted the entire system as an effective and efficient routine inspection measures in 1996. This report describes the modification and reconstruction of

Slow-neutron capture therapy for malignant tumours: its history and recent development

International Nuclear Information System (INIS)

Hatanaka, H.

1975-01-01

Slow-neutron capture therapy was first suggested in 1936. The early clinical trials were performed at Brookhaven National Laboratory and Massachusetts Institute of Technology reactors. In the last series of treatments in 1960 and 1961, none of the 17 glioblastoma patients lived longer than a year and the clinical trial was discontinued, particularly because the was pathological evidence that normal tissue had been seriously damaged. Hatanaka, who worked first with Sweet between 1964 and 1967, continued intensive basic research and organized a collaborating team of chemists, physicists and physicians in Japan where he resumed treatment of brain tumour patients in 1968. The rationale of the revised therapy included: (1) use of promising compounds such as mercaptoundecahydrododecaborate, which has a high tumour binding property, (2) use of adrenocorticoid to minimize vascular damage, (3) intra-arterial infusion of boron to obtain a higher concentration in the tumour, (4) restriction of excessive neutron intensity, (5) and some technical improvements. New research techniques were also introduced, such as alpha autoradiography, electron microscopy, and immunotherapy. With the mercaptoundecahydrododecaborate compound an absolute concentration of 30 μg per gram of tumour is easily attainable, while the blood level of the isotope can be lowered to at least half of the tumour concentration. Normal dog brains were able to tolerate this therapy. Among the 15 patients so far treated, 13 were treated at the Hitachi Training Reactor. Patients, who had undergone repeated surgery as well as excessive irradiation before they came for the therapy, could not recover their full activities, but proved they could enjoy a significant prolongation of their lives. The only two fresh cases of glioblastoma responded so well to the therapy that one has been working as an engineer and the other as a farmer for 3 years without neurological deficits. Recent progress and future potentials of the

Boron neutron capture therapy for advanced and/or recurrent cancers in the oral cavity

International Nuclear Information System (INIS)

Ariyoshi, Yasunori; Shimahara, Masashi; Kimura, Yoshihiro; Miyatake, Shin-ichi; Kuroiwa, Toshihiko; Nagata, Kenji; Sakurai, Yoshinori; Maruhashi, Akira; Ono, Koji

2006-01-01

This preliminary study of 5 patients with advanced and/or recurrent cancer in the oral cavity was performed to evaluate the effectiveness of Boron Neutron Capture Therapy (BNCT). The patients received therapy with the 10 B-carrier p-boronophenylalanine (BPA) with or without borocaptate sodium (BSH) and irradiation thereafter with epithermal neutrons. All underwent 18 F-BPA PET studies before receiving BNCT to determine the accumulation ratios of BPA in tumor and normal tissues. The tumor mass was decreased in size and at minimum a transient partial response was achieved in all cases, though rapid tumor re-growth was observed in 2. Although tentative clinical responses and improvements in quality of life were recognized, obliteration of the tumor was not obtained in any of the cases. Additional studies are required to determine the utility and indication of BNCT for oral cancer. (author)

Investigation of boron conjugated thiouracil derivates for neutron capture therapy of melanoma

International Nuclear Information System (INIS)

Corderoy-Buck, S.; Allen, B.J.; Wilson, J.G.; Tjarks, W.; Gabel, D.; Barkla, D.; Patwardhan, A.; Chandler, A.; Moore, D.E.

1990-01-01

Boron conjugated thiouracil derivatives were investigated as possible agents for boron neutron capture therapy (BNCT) of melanoma. Nude mice bearing human or murine melanoma xenografts were used for biodistribution studies following i.p. or i.t. (intratumoural) injection of these drugs. Boron content was analysed by inductively coupled plasma atomic emission spectrometry. Wide variation between tumour lines was observed with respect to accumulation of these drugs, but they appear to offer potential as melanoma affined boron carriers if solubility problems are overcome by liposome entrapment. Pre-treatment to stimulate melanogenesis may also prove a useful adjunct in achieving the therapeutic concentrations of boron necessary for successful BNCT. 25 refs., 4 tabs., 3 figs

JAERI 20 MV tandem accelerator

International Nuclear Information System (INIS)

Tsukada, Kineo; Harada, Kichinosuke

1977-01-01

Accelerators have been developed as the experimental apparatuses for the studies on nuclei and elementary particles. One direction of the development is the acceleration of protons and electrons to more and more high energy, and another direction is the acceleration of heavy ions up to uranium to several MeV up to several hundreds MeV. However recently, accelerators are used as the useful tools for the studies in wider fields. There are electrostatic acceleration and high frequency acceleration in ion acceleration, and at present, super-large accelerators are high frequency acceleration type. In Japan Atomic Energy Research Institute, it was decided in 1975 to construct an electrostatic accelerator of tandem type in order to accelerate heavy ions. In case of the electrostatic acceleration, the construction is relatively simple, the acceleration of heavy ions is easy, the property of the ion beam is very good, and the energy is stable. Especially, the tandem type is convenient for obtaining high energy. The tandem accelerator of 20 MV terminal voltage was ordered from the National Electrostatics Corp., USA, and is expected to be completed in 1978. The significance of heavy ion acceleration in the development and research of atomic energy, tandem van de Graaff accelerators, the JAERI 20MV tandem accelerator, and the research project with this accelerator are described. (Kako, I.)

Development of large scale fusion plasma simulation and storage grid on JAERI Origin3800 system

International Nuclear Information System (INIS)

Idomura, Yasuhiro; Wang, Xin

2003-01-01

Under the Numerical EXperiment of Tokamak (NEXT) research project, various fluid, particle, and hybrid codes have been developed. These codes require a computational environment which consists of high performance processors, high speed storage system, and high speed parallelized visualization system. In this paper, the performance of the JAERI Origin3800 system is examined from a point of view of these requests. In the performance tests, it is shown that the representative particle and fluid codes operate with 15 - 40% of processing efficiency up to 512 processors. A storage area network (SAN) provides high speed parallel data transfer. A parallel visualization system enables order to magnitude faster visualization of a large scale simulation data compared with the previous graphic workstations. Accordingly, an extremely advanced simulation environment is realized on the JAERI Origin3800 system. Recently, development of a storage grid is underway in order to improve a computational environment of remote users. The storage grid is constructed by a combination of SAN and a wavelength division multiplexer (WDM). The preliminary tests show that compared with the existing data transfer methods, it enables dramatically high speed data transfer ∼100 Gbps over a wide area network. (author)

Present status of decommissioning materials reuse research at JAERI

International Nuclear Information System (INIS)

Fujiki, Kazuo; Nakamura, Hisashi; Kanazawa, Katsuo

1991-01-01

Rational treatment and disposal of a large volume of the dismantling wastes resulting from the reactor dismantling are the key to success to carry out the decommissioning smoothly. From this viewpoint, the Japan Atomic Energy Research Institute (JAERI) has been conducting development of the recycling technology for metal waste and a investigation study on the rational recycling system for the dismantling wastes recycling. With respect to the development of the recycling technology, melting tests using non-contaminated metals have been conducted and the basic characteristics of experimental facility and material balances understood. In the investigation study on the rational recycling system, review and discussion were made on the amount of waste arising from decommissioning a nuclear power plant, a scenario of recycling the wastes, and the necessary processing facilities. (author)

Boron neutron capture therapy for oral precancer: proof of principle in an experimental animal model

Energy Technology Data Exchange (ETDEWEB)

A. Monti Hughes; ECC Pozzi; S. Thorp; M. A. Garabalino; R. O. Farias; S. J. Gonzalez; E. M. Heber; M. E. Itoiz; R. F. Aromando; A. J. Molinari; M. Miller; D. W. Nigg; P. Curotto; V. A. Trivillin; A. E. Schwint

2013-11-01

Field-cancerized tissue can give rise to second primary tumours, causing therapeutic failure. Boron neutron capture therapy (BNCT) is based on biological targeting and would serve to treat undetectable foci of malignant transformation. The aim of this study was to optimize BNCT for the integral treatment for oral cancer, with particular emphasis on the inhibitory effect on tumour development originating in precancerous conditions, and radiotoxicity of different BNCT protocols in a hamster cheek pouch oral precancer model.

Multi-Family Pediatric Pain Group Therapy: Capturing Acceptance and Cultivating Change

Directory of Open Access Journals (Sweden)

Samantha E. Huestis

2017-12-01

Full Text Available Behavioral health interventions for pediatric chronic pain include cognitive-behavioral (CBT, acceptance and commitment (ACT, and family-based therapies, though literature regarding multi-family therapy (MFT is sparse. This investigation examined the utility and outcomes of the Courage to Act with Pain: Teens Identifying Values, Acceptance, and Treatment Effects (CAPTIVATE program, which included all three modalities (CBT, ACT, MFT for youth with chronic pain and their parents. Program utility, engagement, and satisfaction were evaluated via quantitative and qualitative feedback. Pain-specific psychological, behavioral, and interpersonal processes were examined along with outcomes related to disability, quality of life, pain interference, fatigue, anxiety, and depressive symptoms. Participants indicated that CAPTIVATE was constructive, engaging, and helpful for social and family systems. Clinical and statistical improvements with large effect sizes were captured for pain catastrophizing, acceptance, and protective parenting but not family functioning. Similar effects were found for functional disability, pain interference, fatigue, anxiety, and depression. Given the importance of targeting multiple systems in the management of pediatric chronic pain, preliminary findings suggest a potential new group-based treatment option for youth and families. Next steps involve evaluating the differential effect of the program over treatment as usual, as well as specific CBT, ACT, and MFT components and processes that may affect outcomes.

Clinical results of boron neutron capture therapy (BNCT) for glioblastoma

International Nuclear Information System (INIS)

Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, H.

2011-01-01

The purpose of this study was to evaluate the clinical outcome of BSH-based intra-operative BNCT (IO-BNCT) and BSH and BPA-based non-operative BNCT (NO-BNCT). We have treated 23 glioblastoma patients with BNCT without any additional chemotherapy since 1998. The median survival time (MST) of BNCT was 19.5 months, and 2-year, 3-year and 5-year survival rates were 26.1%, 17.4% and 5.8%, respectively. This clinical result of BNCT in patients with GBM is superior to that of single treatment of conventional radiotherapy compared with historical data of conventional treatment. - Highlights: ► In this study, we evaluate the clinical outcome of boron neutron capture therapy (BNCT) for malignant brain tumors. ► We have treated 23 glioblastoma (GBM) patients with BNCT without any additional chemotherapy. ► Clinical results of BNCT in patients with GBM are superior to that of single treatment of conventional radiotherapy compared with historical data of conventional treatment.

Clinical treatment planning for subjects undergoing boron neutron capture therapy at Harvard-MIT

International Nuclear Information System (INIS)

Zamenhof, R.G.; Palmer, M.R.; Buse, P.M.

2001-01-01

Treatment planning is a crucial component of the Harvard-MIT boron neutron capture therapy (BNCT) clinical trials. Treatment planning can be divided into five stages: (1) pre-planning, based on CT and MRI scans obtained when the subject arrives at the hospital and on assumed boron-10 distribution parameters; (2) subject set-up, or simulation, in the MITR-II medical therapy room to determine the boundary conditions for possible set-up configurations; (3) re-planning, following the subject simulation; (4) final localization of the subject in the medical therapy room for BNCT; and (5) final post facto recalculation of the doses delivered based on firm knowledge of the blood boron-10 concentration profiles and the neutron flux histories from precise online monitoring. The computer-assisted treatment planning is done using a specially written BNCT treatment planning code called MacNCTPLAN. The code uses the Los Alamos National Laboratory's Monte Carlo n-particle radiation transport code MCNPv.4b as the dose calculation engine and advanced anatomical model simulation based on an automatic evaluation of CT scan data. Results are displayed as isodose contours and dose-volume histograms, the latter correlated precisely with corresponding anatomical CT or MRI image planes. Examples of typical treatment planning scenarios will be presented. (author)

Some considerations on a plasma in the JAERI experimental fusion reactor

International Nuclear Information System (INIS)

Tone, T.; Yamato, H.; Maki, K.

1976-01-01

The preliminary analysis of the plasma characteristics for the JAERI tokamak experimental fusion reactor is reported. In order to make the reactor compact, the self-sustaining condition has been removed. Stationary heating by 200 keV neutral deuteron beam to maintain the power balance is applied expecting the power amplification by the TCT effect. The main parameters determined are power output of 100 MW, toroidal field on axis of 6 T, aspect ratio of 4.5 and major radius of 6.75 m. The results of the plasma power balance, fueling by means of the gas blanket scheme, power stabilization with feedback and the start-up are presented

The Idaho Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program overview

International Nuclear Information System (INIS)

Dorn, R.V. III; Griebenow, M.L.; Ackermann, A.L.; Miller, L.G.; Miller, D.L.; Wheeler, F.J.; Bradshaw, K.M.; Wessol, D.E.; Harker, Y.D.; Nigg, D.W.; Randolph, P.D.; Bauer, W.F.; Gavin, P.R.; Richards, T.L.

1992-01-01

The Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program has been funded since 1988 to evaluate brain tumor treatment using Na 2 B 12 H 11 SH (borocaptate sodium or BSH) and epithermal neutrons. The PBF/BNCT Program pursues this goal as a comprehensive, multidisciplinary, multiorganizational endeavor applying modern program management techniques. The initial focus was to: (1) establish a representative large animal model and (2) develop the generic analytical and measurement capabilities require to control treatment repeatability and determine critical treatment parameters independent of tumor type and body location. This paper will identify the PBF/BNCT Program elements and summarize the status of some of the developed capabilities

Synthesis and biological evaluation of boronated polyglycerol dendrimers as potential agent for neutron capture therapy

International Nuclear Information System (INIS)

Silva, Gerald S.; Camillo, Maria A.P.; Higa, Olga Z.; Pugliesi, Reynaldo; Fermamdes, Edson G.R.; Queiroz, Alvaro A.A. de

2005-01-01

In this work, the polyglycerol dendrimer (PGLD) generation 5 was used to obtain a boronated macromolecule for boron neutron capture therapy. The PGLD dendrimer was synthesized by the ring opening polymerization of deprotonated glycidol using polyglycerol as core functionality in a step-growth processes denominated divergent synthesis. The PGLD dendritic structure was confirmed by gel permeation chromatography, nuclear magnetic resonance ( 1 H-NMR, 13 C-NMR) and matrix assisted laser desorption/ionization techniques. The synthesized dendrimer presented low dispersion in molecular weights (M w /M n = 1.05) and a degree of branching of 0.82, which characterize the polymer dendritic structure. Quantitative neutron capture radiography was used to investigate the boron-10 enrichment of the polyglycerol dendrimer. The in vitro cytotoxicity to Chinese hamster ovary cells of 10 B-PGLD dendrimer indicate lower cytotoxicity, suggesting that the macromolecule is a biocompatible material. (author)

Research related to boron neutron capture therapy at The Ohio State University

International Nuclear Information System (INIS)

Barth, R.F.; Soloway, A.H.; Alam, F.

1986-01-01

Research in the area of boron neutron capture therapy (BNCT) at The Ohio State University is a highly multidisciplinary effort involving approximately twenty investigators in nine different departments. Major areas of interest include: (1) Boronation of monoclonal antibodies directed against tumor-associated antigens for the delivery of 10 B; (2) Synthesis of 10 B-containing derivatives of promazines and porphyrins that possess tumor-localizing properties; (3) Development of a rat model for the treatment of glioblastoma by BNCT; (4) Quantitation and microdistribution of 10 B in tissues by means of a solid state nuclear track detector. The ultimate goal of this research is to carry out the extensive preclinical studies that are required to bring BNCT to the point of a clinical trial. 13 references

Optimal Neutron Source and Beam Shaping Assembly for Boron Neutron Capture Therapy

International Nuclear Information System (INIS)

Vujic, J.; Greenspan, E.; Kastenber, W.E.; Karni, Y.; Regev, D.; Verbeke, J.M.; Leung, K.N.; Chivers, D.; Guess, S.; Kim, L.; Waldron, W.; Zhu, Y.

2003-01-01

There were three objectives to this project: (1) The development of the 2-D Swan code for the optimization of the nuclear design of facilities for medical applications of radiation, radiation shields, blankets of accelerator-driven systems, fusion facilities, etc. (2) Identification of the maximum beam quality that can be obtained for Boron Neutron Capture Therapy (BNCT) from different reactor-, and accelerator-based neutron sources. The optimal beam-shaping assembly (BSA) design for each neutron source was also to e obtained. (3) Feasibility assessment of a new neutron source for NCT and other medical and industrial applications. This source consists of a state-of-the-art proton or deuteron accelerator driving and inherently safe, proliferation resistant, small subcritical fission assembly

Status and future program of reactor physics experiments in JAERI Critical facilities, FCA and TCA

International Nuclear Information System (INIS)

Okajima, Shigeaki; Osugi, Toshitaka; Nakajima, Ken; Suzaki, Takenori; Miyoshi, Yoshinori

1999-01-01

The critical facilities in JAERI, FCA (Fast Critical Assembly) and TCA (Tank-type Critical Assembly), have been used to provide integral data for evaluation of nuclear data as well as for development of various types of reactor since they went critical in 1960's. In this paper a review is presented on the experimental programs in both facilities. And the experimental programs in next 5 years are also shown. (author)

Outline of application plans of accelerator beams in JAERI

Energy Technology Data Exchange (ETDEWEB)

Suzuki, Yasuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

Japan Atomic Energy Research Institute (JAERI) has various application plans of accelerators such as; Neutron Science Research Complex (NSRC), Positron Factory, International Fusion Material Irradiation Facility (IFMIF), and Spring-8 Project. Each application plan has its own research program and its own core accelerator. The NSRC is a multi-purpose research complex composed of seven research facilities: slow neutron scattering facility for material science, the nuclear energy research facility like nuclear transmutation and so on. The Positron Factory will be applied to the research of precise analysis of material structure by novel method of positron probing. The IFMIF aims at simulating the wall loading of a demo fusion reactor by producing high intense neutron flux. The SPring-8 is the largest synchrotron radiation source in the world. More than 60 X-ray beam lines will be equipped for the various researches. (author)

Preparation and certification of certified reference materials JAERI-Z21, Z22 and Z23 for analysis of zirconium and its alloys

International Nuclear Information System (INIS)

Takashima, Kyoichiro

1991-03-01

The Sub-Committee on Chemical Analysis of Nuclear Materials was organized in April 1987, under the Committee on Analytical Chemistry of Nuclear Fuels and Reactor Materials, JAERI, for renewal of certified reference materials of zirconium base alloys and zirconium metal. Collaborative analysis was carried out among ten participating laboratories for the certification of the JAERI CRMs Z21 to Z23. As a results of the collaborative works, the certified values for sixteen elements (Sn, Fe, Ni, Cr, Hf, Al, Si, Co, Cu, Ti, Mn, Pb, U, Cd, B and W) in the CRMs were given. In this report, preparation of raw materials, homogeneity test, chemical analysis for certification by collaborative works during April 1987 to March 1990 are described. (author)

Analysis of MCNP simulated gamma spectra of CdTe detectors for boron neutron capture therapy.

Science.gov (United States)

Winkler, Alexander; Koivunoro, Hanna; Savolainen, Sauli

2017-06-01

The next step in the boron neutron capture therapy (BNCT) is the real time imaging of the boron concentration in healthy and tumor tissue. Monte Carlo simulations are employed to predict the detector response required to realize single-photon emission computed tomography in BNCT, but have failed to correctly resemble measured data for cadmium telluride detectors. In this study we have tested the gamma production cross-section data tables of commonly used libraries in the Monte Carlo code MCNP in comparison to measurements. The cross section data table TENDL-2008-ACE is reproducing measured data best, whilst the commonly used ENDL92 and other studied libraries do not include correct tables for the gamma production from the cadmium neutron capture reaction that is occurring inside the detector. Furthermore, we have discussed the size of the annihilation peaks of spectra obtained by cadmium telluride and germanium detectors. Copyright © 2017 Elsevier Ltd. All rights reserved.

Biological models in vivo for boron neutronic capture studies as tumors therapy

International Nuclear Information System (INIS)

Kreimann, Erica L.; Dagrosa, Maria A.; Schwint, Amanda E.; Itoiz, Maria E.; Pisarev, Mario A.; Farias, Silvia S.; Garavaglia, Ricardo N.; Batistoni, Daniel A.

1999-01-01

The use of experimental models for Boron Neutronic Capture studies as Tumors Therapy have as two main objectives: 1) To contribute to the basic knowledge of the biological mechanisms involved to increase the method therapeutical advantage, and 2) To explore the possible application of this therapeutic method to other pathologies. In this frame it was studied the carcinogenesis model of hamster cheek pouch, a type of human buccal cancer. Biodistribution studies of boron compound were performed in tumor, blood and in different precancerous and normal tissues as well as BNCT studies. Results validated this method for BNCT studies and show the capacity of the oral mucosa tumors of selectively concentrate the boron compound, showing a deleterious clear effect on the tumor after 24 hours with BNCT treatment. (author)

Boron neutron capture therapy induces cell cycle arrest and DNA fragmentation in murine melanoma cells

Energy Technology Data Exchange (ETDEWEB)

Faiao-Flores, F. [Biochemical and Biophysical Laboratory, Butantan Institute, 1500 Vital Brasil Avenue, Sao Paulo (Brazil)] [Faculty of Medicine, University of Sao Paulo, 455 Doutor Arnaldo Avenue, Sao Paulo (Brazil); Coelho, P.R.P. [Institute for Nuclear and Energy Research, 2242 Lineu Prestes Avenue, Sao Paulo (Brazil); Arruda-Neto, J. [Physics Institute, University of Sao Paulo, 187 Matao Street, Sao Paulo (Brazil)] [FESP, Sao Paulo Engineering School, 5520 Nove de Julho Avenue, Sao Paulo (Brazil); Maria, Durvanei A., E-mail: durvaneiaugusto@yahoo.br [Biochemical and Biophysical Laboratory, Butantan Institute, 1500 Vital Brasil Avenue, Sao Paulo (Brazil)

2011-12-15

The melanoma is a highly lethal skin tumor, with a high incidence. Boron Neutron Capture Therapy (BNCT) is a radiotherapy which combines Boron with thermal neutrons, constituting a binary system. B16F10 melanoma and L929 fibroblasts were treated with Boronophenylalanine and irradiated with thermal neutron flux. The electric potential of mitochondrial membrane, cyclin D1 and caspase-3 markers were analyzed. BNCT induced a cell death increase and cyclin D1 amount decreased only in B16F10 melanoma. Besides, there was not caspase-3 phosphorylation.

Possible application of boron neutron capture therapy to canine osteosarcoma

International Nuclear Information System (INIS)

Takeuchi, Akira

1985-01-01

Possibility for successful treatment of canine osteosarcoma by boron neutron capture therapy (BNCT) was demonstrated based upon an uptake study of the boron compound and an experimental treatment by BNCT. In the up take study following intravenous administration of Na 2 B 12 H 11 SH, satisfactorily higher boron concentration with some variation between tumors is likely to be obtained 12 hours after the administration, together with significantly lower boron levels in blood and bone. Based upon these results, osteosarcoma of a mongrel dog was successfully treated by BNCT. The tumor received approximately 3800 rads with single neutron irradiation (approximately 1.4 x 10 13 n./cm 2 ) about 12 hours after intravenous infusion of Na 2 B 12 H 11 SH of 96 % enriched 10 B in the ratio of 50 mg 10 B/kg. Clinical and radiographical improvements were remarkable and no neoplastic cell was found in any part of the original neoplastic lesion and its surrounding tissue at the time of autopsy after 30 days. (author)

Irradiation system for neutron capture therapy using the small accelerator

International Nuclear Information System (INIS)

Kobayashi, Tooru; Hoshi, Masaharu

2002-01-01

Neutron capture therapy (NCT) is to kill tumor cells that previously incorporated the stable isotope which generates heavy charged particles with a short range and a high linear energy transfer (LET) on neutron irradiation. Boron-10 is ordinarily used as such an isotope. The tumor tissue is neutron-irradiated at craniotomy after preceding craniotomy for tumor extraction: therefore two surgeries are required for the present NCT in Japan. The reactions 10 B(n, αγ) 7 Li and 7 Li (p, n) 7 Be are thought preferential for patients and doctors if a convenient small accelerator, not the reactor used at present, is available in the hospital because only one craniotomy is sufficient. Authors' examinations of the system for NCT using the small accelerator involve irradiation conditions, desirable energy spectrum of neutron, characterization of thermal and epi-thermal neutrons, social, practical and technical comparison of the reactor and accelerator, and usefulness of the reaction 7 Li (p, n) 7 Be. The system devoted to the NCT is awaited in future. (K.H.)

Application of adjoint Monte Carlo to accelerate simulations of mono-directional beams in treatment planning for Boron Neutron Capture Therapy

NARCIS (Netherlands)

Nievaart, V.A.; Legrady, D.; Moss, R.L.; Kloosterman, J.L.; Van der Hagen, T.H.; Van Dam, H.

2007-01-01

This paper deals with the application of the adjoint transport theory in order to optimize Monte Carlo based radiotherapy treatment planning. The technique is applied to Boron Neutron Capture Therapy where most often mixed beams of neutrons and gammas are involved. In normal forward Monte Carlo

Report of evaluation on socio-economic effects of R and D results in Japan Atomic Energy Research Institute (JAERI)

International Nuclear Information System (INIS)

2002-08-01

Japan Atomic Energy Research Institute (JAERI), as a core organization devoted to comprehensive nuclear energy research, has steadily promoted nuclear energy research aiming at long-term and stable supply of energy supporting the basis of national existence, advanced nuclear science and engineering leading to increase in Japanese industrial competitive power, etc. Through these undertaking, JAERI has produced a lot of remarkable achievements to contribute the national requests mentioned above. In total, about 1.8 trillion-yen of national funds and over 60,000 person · years of researchers and technical staffs have been invested in the R and D's for the past 45 years. Recently it has been argued and recognized to evaluate how the profits of R and D results in public research institutes supported by national funds are returned to the Japanese people as taxpayers and society as part of an administrative and financial reform. Then, seeing its 45th anniversary, JAERI has tried to evaluate the effects of the R and D achievements on the Japanese society and economy apart from the reviews on the management of the organization and research results by the ex-house experts from the viewpoints of specialty and technical aspects. In order to execute the aforementioned evaluation, JAERI established the in-house Ad hoc Committee for Evaluation of R and D Achievements where decision of the evaluation plan is made, in July 2001, and executed the evaluation followed by assembling the necessary database collected from individual branches. Results obtained from these activities were finally summarized in the Ad hoc Committee. Because a methodology for quantitative evaluation of the economical effects, i.e. cost-benefit effects of R and D's was not established yet, the evaluation was prudently carried out with the assistance of three think tanks and under advices by three ex-house experts. R and D's in JAERI are not limited to the ones where benefits corresponding to profits can be

Development of a multi-ampere H- ion source at JAERI

International Nuclear Information System (INIS)

Inoue, T.; Hanada, M.; Mizuno, M.; Ohara, Y.; Okumura, Y.; Suzuki, Y.; Tanaka, M.; Watanabe, K.

1992-01-01

Recent results of R ampersand D on high current negative ion source at JAERI are presented. After succeeding in ten ampere H - ion beam production, the R ampersand D work has been progressed toward longer pulse beam production and the beam optics. A long pulse operation for 24 hours was demonstrated stably with a small cesiated volume source. It was confirmed that the heat load in the source is a modest level allowable for the long pulse operation. The cesium effect lasted for 24 hours, once the cesium was seeded before operation. In beam optics study, we have produced a beam with very small divergent angle of 1.5 mrad. To take this advantage for a design of compact neutral beam system, beamlet focusing technique by aperture displacement was applied in the H - beam extractor

Development of the four group partitioning process at JAERI

International Nuclear Information System (INIS)

Kubota, Masumitsu; Morita, Yasuji; Yamaguchi, Isoo; Yamagishi, Isao; Fujiwara, T.; Watanabe, Masayuki; Mizoguchi, Kenichi; Tatsugae, Ryozo

1999-01-01

At JAERI, development of a partitioning method started about 24 years ago. From 1973 to 1984, a partitioning process was developed for separating elements in HLLW into 3 groups; TRU, Sr-Cs and others. The partitioning process consisted of three steps; solvent extraction of U and Pu with TBP, solvent extraction of Am and Cm with DIDPA, and adsorption of Sr and Cs with inorganic ion exchangers. The process was demonstrated with real HLLW. Since 1985, a four group partitioning process has been developed, in which a step for separating the Tc-PGM group was developed in addition to the three group separation. Effective methods for separating TRU, especially Np, and Tc have been developed. In this paper, the flow sheet of the four group partitioning and the results of tests with simulated and real HLLW in NUCEF hot-cell are shown. (J.P.N.)

Boron Neutron Capture Therapy in the Treatment of Locally Recurred Head and Neck Cancer

International Nuclear Information System (INIS)

Kankaanranta, Leena; Seppaelae, Tiina; Koivunoro, Hanna; Saarilahti, Kauko; Atula, Timo; Collan, Juhani; Salli, Eero; Kortesniemi, Mika; Uusi-Simola, Jouni; Maekitie, Antti; Seppaenen, Marko; Minn, Heikki; Kotiluoto, Petri; Auterinen, Iiro; Savolainen, Sauli; Kouri, Mauri; Joensuu, Heikki

2007-01-01

Purpose: Head and neck carcinomas that recur locally after conventional irradiation pose a difficult therapeutic problem. We evaluated safety and efficacy of boron neutron capture therapy (BNCT) in the treatment of such cancers. Methods and Materials: Twelve patients with inoperable, recurred, locally advanced (rT3, rT4, or rN2) head and neck cancer were treated with BNCT in a prospective, single-center Phase I-II study. Prior treatments consisted of surgery and conventionally fractionated photon irradiation to a cumulative dose of 56-74 Gy administered with or without concomitant chemotherapy. Tumor responses were assessed using the RECIST (Response Evaluation Criteria in Solid Tumors) criteria and adverse effects using the National Cancer Institute common toxicity grading v3.0. Intravenously administered boronophenylalanine-fructose (BPA-F, 400 mg/kg) was used as the boron carrier. Each patient was scheduled to be treated twice with BNCT. Results: Ten patients received BNCT twice; 2 were treated once. Ten (83%) patients responded to BNCT, and 2 (17%) had tumor growth stabilization for 5.5 and 7.6 months. The median duration of response was 12.1 months; six responses were ongoing at the time of analysis or death (range, 4.9-19.2 months). Four (33%) patients were alive without recurrence with a median follow-up of 14.0 months (range, 12.8-19.2 months). The most common acute adverse effects were mucositis, fatigue, and local pain; 2 patients had a severe (Grade 3) late adverse effect (xerostomia, 1; dysphagia, 1). Conclusions: Boron neutron capture therapy is effective and safe in the treatment of inoperable, locally advanced head and neck carcinomas that recur at previously irradiated sites

Present status and future perspective of research and test reactors in JAERI

International Nuclear Information System (INIS)

Baba, Osamu; Kaieda, Keisuke

1999-01-01

Since 1957, Japan Atomic Energy Research Institute (JAERI) has constructed several research and test reactors to fulfil a major role in the study of nuclear energy and fundamental research. At present, four reactors, the Japan Research Reactor No. 3 and No. 4 (JRR-3M and JRR-4 respectively), the Japan Materials Testing Reactor (JMTR) and the Nuclear Safety Research Reactor (NSRR), are in operation, and a new High Temperature Engineering Test Reactor (HTTR) has reached first criticality and is waiting for the power-up test. This paper introduce these reactors and describe their present operational status. The recent tendency of utilization and future perspectives are also reported. (author)

Present status and future perspective of research and test reactors in JAERI

Energy Technology Data Exchange (ETDEWEB)

Baba, Osamu [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Kaieda, Keisuke

1999-08-01

Since 1957, Japan Atomic Energy Research Institute (JAERI) has constructed several research and test reactors to fulfil a major role in the study of nuclear energy and fundamental research. At present, four reactors, the Japan Research Reactor No. 3 and No. 4 (JRR-3M and JRR-4 respectively), the Japan Materials Testing Reactor (JMTR) and the Nuclear Safety Research Reactor (NSRR), are in operation, and a new High Temperature Engineering Test Reactor (HTTR) has reached first criticality and is waiting for the power-up test. This paper introduce these reactors and describe their present operational status. The recent tendency of utilization and future perspectives are also reported. (author)

A review of research and development on accelerator-driven system for transmutation of long-lived nuclear waste at JAERI

International Nuclear Information System (INIS)

Oigawa, H.

2004-01-01

The dedicated transmutation system using the accelerator driven subcritical system (ADS) has been studied in the Japan Atomic Energy Research Institute (JAERI) to reduce the burden of the final disposal of the nuclear waste. A subcritical reactor with the thermal power of 800 MW is proposed, where 250 kg of minor actinide (MA) can be transmuted annually. A superconducting linear accelerator (LINAC) with the beam power of 20-30 MW is necessary for this ADS. Lead-bismuth eutectic (LBE) is used for both the spallation target and the core coolant. Many research and development activities including the design study are under way and planned at JAERI to examine the feasibility of the ADS. In the design study, optimization of the ADS design is under way in terms of neutronics and structural feasibility. In the field of the proton accelerator, a superconducting LINAC is being developed. In the field of the LBE technology, material compatibility, thermal-hydraulics and polonium behavior are being studied. The irradiation effect of structural material to be used for the beam window is also being studied. In the field of the reactor physics of the subcritical core fueled with MA, the reliability of nuclear data is examined and the subcriticality monitoring technique is being investigated. Moreover, in the framework of J-PARC project (Japan Proton Accelerator Research Complex), JAERI plans to construct the Transmutation Experimental Facility (TEF) to demonstrate the feasibility of the ADS with using high-energy proton beam, to accumulate valuable knowledge about reactor physics and operation of ADS, and to establish a database for LBE spallation target and relevant materials. (author)

Development of an optical resonator with high-efficient output coupler for the JAERI far-infrared free-electron laser

International Nuclear Information System (INIS)

Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki; Sawamura, Masaru; Kikuzawa, Nobuhiro; Shizuma, Toshiyuki; Minehara, Eisuke

2001-01-01

An optical resonator with a high-efficient output coupler was developed for the JAERI far-infrared free-electron laser. The optical resonator is symmetrical near-concentric geometry with an insertable scraper output coupler. As a result of the development of the optical resonator, the JAERI-FEL has been successfully, lased with averaged power over 1 kW. Performance of the optical resonator with the output coupler was evaluated at optical wavelength of 22 μm by using an optical mode calculation code. The output coupling and diffractive loss with a dominant eigen-mode of the resonator were calculated using an iterative computation called Fox-Li procedure. An efficiency factor of the optical resonator was introduced for the evaluation of the optical resonator performance. The efficiency factor was derived by the amount of the output coupling and diffractive loss of the optical resonator. It was found that the optical resonator with the insertable scraper coupler was the most suitable to a high-power and high-efficient far-infrared free-electron laser. (author)

A shielding design for an accelerator-based neutron source for boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Hawk, A.E.; Blue, T.E. E-mail: blue.1@osu.edu; Woollard, J.E

2004-11-01

Research in boron neutron capture therapy (BNCT) at The Ohio State University Nuclear Engineering Department has been primarily focused on delivering a high quality neutron field for use in BNCT using an accelerator-based neutron source (ABNS). An ABNS for BNCT is composed of a proton accelerator, a high-energy beam transport system, a {sup 7}Li target, a target heat removal system (HRS), a moderator assembly, and a treatment room. The intent of this paper is to demonstrate the advantages of a shielded moderator assembly design, in terms of material requirements necessary to adequately protect radiation personnel located outside a treatment room for BNCT, over an unshielded moderator assembly design.

JAERI tandem-accelerator and tandem-booster

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Tadashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-03-01

In 1982, aiming at the new development of atomic energy research, the tandem accelerator of Japan Atomic Energy Research Institute (JAERI) was installed. In fiscal year 1993, the superconducting boosters which can increase the ion energy by up to 4 times were added, and the research in the region below 1000 MeV became possible. Those are electrostatic type accelerators which are easy to be used especially in basic research field, and are useful for future research. The tandem accelerator has been operated while maintaining the first class performance as the accelerator for various kinds of heavy ion beam. It has the special shape among electrostatic type accelerators, and is excellent in the easiness of control and stability. The main particulars of the tandem accelerator are shown. As for the ion sources of the tandem accelerator, three cesium sputter type ion sources are installed on two high voltage stands. The kinds of the ions which can be accelerated are mainly negative ions. As the improvement, electron cyclotron resonance (ECR) ion sources are expected to be adopted. As for the tandem boosters, the 1/4 wavelength type resonance hollow cylinder was adopted. The constitution of the tandem boosters is explained. The way of utilizing the tandem accelerator system and the aim for hereafter are reported. (K.I.)

Overview of HTGR utilization system developments at JAERI

International Nuclear Information System (INIS)

Miyamoto, Y.; Shiozawa, S.; Inagaki, Y.

1997-01-01

JAERI has been constructing a 30-MWt HTGR, named HTTR, to develop technology and to demonstrate effectiveness of high-temperature nuclear heat utilization. A hydrogen production system by natural gas steam reforming is to be the first heat utilization system of the HTTR since its technology matured in fossil-fired plant enables to couple with HTTR in the early 2000's and technical solutions demonstrated by the coupling will contribute to all other hydrogen production systems. The HTTR steam reforming system is designed to utilize the nuclear heat effectively and to achieve hydrogen productivity competitive to that of a fossil-fired plant with operability, controllability and safety acceptable enough to commercialization, and an arrangement of key components was already decided. Prior to coupling of the steam reforming system with the HTTR, an out-of-pile test is planned to confirm safety, controllability and performance of the steam reforming system under simulated operational conditions. The out-of-pile system is an approximately 1/20-1/30 scale system of the HTTR steam reforming system and simulates key components downstream from an IHX

The 3D tomographic image reconstruction software for prompt-gamma measurement of the boron neutron capture therapy

International Nuclear Information System (INIS)

Morozov, Boris; Auterinen, Iiro; Kotiluoto, Petri; Kortesniemi, Mika

2006-01-01

A tomographic imaging system based on the spatial distribution measurement of the neutron capture reaction during Boron Neutron Capture Therapy (BNCT) would be very useful for clinical purpose. Using gamma-detectors in a 2D-panel, boron neutron capture and hydrogen neutron capture gamma-rays emitted by the neutron irradiated region can be detected, and an image of the neutron capture events can be reconstructed. A 3D reconstruction software package has been written to support the development of a 3D prompt-gamma tomographic system. The package consists of three independent modules: phantom generation, reconstruction and evaluation modules. The reconstruction modules are based on algebraic approach of the iterative reconstruction algorithm (ART), and on the maximum likelihood estimation method (ML-EM). In addition to that, two subsets of the ART, the simultaneous iterative reconstruction technique (SIRT) and the component averaging algorithms (CAV) have been included to the package employing parallel codes for multiprocessor architecture. All implemented algorithms use two different field functions for the reconstruction of the region. One is traditional voxel function, another is, so called, blob function, smooth spherically symmetric generalized Kaiser-Bessel function. The generation module provides the phantom and projections with background by tracing the prompt gamma-rays for a given scanner geometry. The evaluation module makes statistical comparisons between the generated and reconstructed images, and provides figure-of-merit (FOM) values for the applied reconstruction algorithms. The package has been written in C language and tested under Linux and Windows platforms. The simple graphical user interface (GUI) is used for command execution and visualization purposed. (author)

Development of in-air micro-PIXE analysis and data sharing systems in JAERI Takasaki

International Nuclear Information System (INIS)

Sakai, Takuro; Kamiya, Tomihiro; Oikawa, Masakazu

2000-01-01

An external scanning ion microbeam system has been developed for in-air micro-PIXE analysis at JAERI Takasaki. The analysis system is widely used for various researches in recent years. The system consists of the external scanning ion microbeam system, a multi-parameter data acquisition system, a file transfer protocol (FTP) server and analysis software. The software of the system provides a graphical user interface for interaction between users and an experimental setup. The server is connected to the Internet and allows remote users to access the experimental data. (author)

The muon science facility at the JAERI/KEK joint project

International Nuclear Information System (INIS)

Miyake, Y.; Nishiyama, K.; Makimura, S.; Kawamura, N.; Shimomura, K.; Kadono, R.; Higemoto, W.; Fukuchi, K.; Beveridge, J.L.; Ishida, K.; Matsuzaki, T.; Watanabe, I.; Matsuda, Y.; Sakamoto, S.; Nakamura, S.N.; Nagamine, K.

2003-01-01

The Muon Science Facility is one of the experimental arenas of the JAERI/KEK Joint Project, which also includes neutron science, particle and nuclear physics, neutrino physics and nuclear transmutation science. Following the recommendations by the review committees, the Joint Project was finally approved for construction at the end of December, 2000. The approval is for Phase 1 of 1335 Oku Yen out of the total project cost of 1890 Oku Yen. It is planned to locate the muon science experimental area together with the neutron facility in an integrated building, as a facility for materials and life science studies. Because its construction will be started in April 2003, we are now working to complete the detailed design of the building structure, shielding, electrical services, cooling water, primary proton beam line, one muon target and secondary beam lines

Boron neutron capture therapy for malignant brain tumor in Japan

Energy Technology Data Exchange (ETDEWEB)

Nakagawa, Yoshinobu [National Kagawa Children`s Hospital, Takamatsu, Kagawa (Japan)

1998-03-01

Since 1968, we have treated 149 patients and performed boron-neutron capture therapy (BNCT) on 164 occasions using 5 reactors in Japan. There were 64 patients with glioblastoma, 39 patients with anaplastic astrocytoma and 17 patients with low grade astrocytoma (grade 1 or 2). There were 30 patients with other types of tumor. The overall response rate in the glioma patients was 64%. Seven patients (12%) of glioblastoma, 22 patients (56%) of anaplastic astrocytoma and 8 patients (62%) of low grade astrocytoma lived more than 2 years Median survival time of glioblastoma was 640 days. Median survival times of patients with anaplastic astrocytoma was 1811 days, and 1669 days in low grade astrocytoma. Six patients (5 glioblastoma and one anaplastic astrocytoma) died within 90 days after BNCT. Six patients lived more than 10 years. Histological grading, age of the patients, neutron fluence at the target point and target depth or size of the tumor were proved to be important factors. BNCT is an effective treatment for malignant brain tumors. We are now became able to radiate the tumor more correctly with a high enough dose of neutron beam even if we use thermal neutron beam. (author)

Electrostatic design and beam transport for a folded tandem electrostatic quadrupole accelerator facility for accelerator-based boron neutron capture therapy

International Nuclear Information System (INIS)

Thatar Vento, V.; Bergueiro, J.; Cartelli, D.; Valda, A.A.; Kreiner, A.J.

2011-01-01

Within the frame of an ongoing project to develop a folded Tandem-Electrostatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT), we discuss here the electrostatic design of the machine, including the accelerator tubes with electrostatic quadrupoles and the simulations for the transport and acceleration of a high intensity beam.

Neutron scattering equipments in JAERI. Current status

International Nuclear Information System (INIS)

Hamaguchi, Yoshikazu; Minakawa, Nobuaki

2003-01-01

24 neutron scattering instruments are installed in the JRR-3M research reactor. Among them JAERI has 12 neutron scattering instruments. Those instruments are HRPD for high-resolution structural analysis, TAS-1 and TAS-2 for elastic and inelastic scattering and for magnetic scattering measurements by the polarized neutron, LTAS for elastic and inelastic scattering measurement at a low energy region, and for neutron device development, PNO for topography and for very small angle scattering measurement in a small Q range, NRG for neutron radiography, RESA for internal strain measurements, SANS for the molecule and semi-macroscopic magnetic structural analysis, BIX-2 and BIX-3 for the biological structural analysis research, and PGA for the research of prompt gamma-ray analysis. The university groups have 12 neutron scattering instruments. Since those instruments were installed at the period when JRR-3M was completed, about 10 years have passed. In order to match the old control systems with the progress of recent computer technologies, and peripheral equipment, numbers of instruments are being renewed. In the neutron guide hall of JRR-3M, the Ni mirror guide tube was replaced by a super mirror guide tube to increase neutron flux. The intensity of 2A flux was increased by a factor of about two. (J.P.N.)

Boron neutron capture therapy of ocular melanoma and intracranial glioma using p-boronophenylalanine

International Nuclear Information System (INIS)

Coderre, J.A.; Greenberg, D.; Micca, P.L.; Joel, D.D.; Saraf, S.; Packer, S.

1990-01-01

During conventional radiotherapy, the dose that can be delivered to the tumor is limited by the tolerance of the surrounding normal tissue within the treatment volume. Boron Neutron Capture Therapy (BNCT) represents a promising modality for selective tumor irradiation. The key to effective BNCT is selective localization of 10 B in the tumor. We have shown that the synthetic amino acid p-boronophenylalanine (BPA) will selectively deliver boron to melanomas and other tumors such as gliosarcomas and mammary carcinomas. Systemically delivered BPA may have general utility as a boron delivery agent for BNCT. In this paper, BNCT with BPA is used in treatment of experimentally induced gliosarcoma in rats and nonpigmented melanoma in rabbits. The tissue distribution of boron is described, as is response to the BNCT. 6 refs., 4 figs., 1 tab

Hyper-thermal neutron irradiation field for neutron capture therapy

International Nuclear Information System (INIS)

Sakurai, Yoshinori; Kobayashi, Tooru; Kanda, Keiji

1994-01-01

The utilization of hyper-thermal neutrons, which have an energy spectrum of a Maxwell distribution higher than the room temperature of 300 K, has been studied in order to improve the thermal neutron flux distribution in a living body for a deep-seated tumor in neutron capture therapy (NCT). Simulation calculations using MCNP-V3 were carried out in order to investigate the characteristics of the hyper-thermal neutron irradiation field. From the results of simulation calculations, the following were confirmed: (i) The irradiation field of the hyper-thermal neutrons is feasible by using some scattering materials with high temperature, such as Be, BeO, C, SiC and ZrH 1.7 . Especially, ZrH 1.7 is thought to be the best material because of good characteristics of up-scattering for thermal neutrons. (ii) The ZrH 1.7 of 1200 K yields the hyper-thermal neutrons of a Maxwell-like distribution at about 2000 K and the treatable depth is about 1.5 cm larger comparing with the irradiation of the thermal neutrons of 300 K. (iii) The contamination by the secondary gamma-rays from the scattering materials can be sufficiently eliminated to the tolerance level for NCT through the bismuth layer, without the larger change of the energy spectrum of hyper-thermal neutrons. ((orig.))

Current status of accelerator-based boron neutron capture therapy

International Nuclear Information System (INIS)

Kreiner, A. J.; Bergueiro, J.; Di Paolo, H.; Castell, W.; Vento, V. Thatar; Cartelli, D.; Kesque, J.M.; Valda, A.A.; Ilardo, J.C.; Baldo, M.; Erhardt, J.; Debray, M.E.; Somacal, H.R.; Estrada, L.; Sandin, J.C. Suarez; Igarzabal, M.; Huck, H.; Padulo, J.; Minsky, D.M.

2011-01-01

The direct use of proton and heavy ion beams for radiotherapy is a well established cancer treatment modality, which is becoming increasingly widespread due to its clear advantages over conventional photon-based treatments. This strategy is suitable when the tumor is spatially well localized. Also the use of neutrons has a long tradition. Here Boron Neutron Capture Therapy (BNCT) stands out, though on a much smaller scale, being a second-generation promising alternative for tumors which are diffuse and infiltrating. On this sector, so far only nuclear reactors have been used as neutron sources. In this paper we describe the current situation worldwide as far as the use of accelerator-based neutron sources for BNCT is concerned (so-called Accelerator-Based (AB)-BNCT). In particular we discuss the present status of an ongoing project to develop a folded Tandem-ElectroStatic-Quadrupole (TESQ) accelerator at the Atomic Energy Commission of Argentina. The project goal is a machine capable of delivering 30 mA of 2.4 MeV protons to be used in conjunction with a neutron production target based on the 7 Li(p,n) 7 Be reaction. These are the specifications needed to produce sufficiently intense and clean epithermal neutron beams to perform BNCT for deep-seated tumors in less than an hour. (author)

Application of generalized perturbation theory to sensitivity analysis in boron neutron capture therapy

International Nuclear Information System (INIS)

Garcia, Vanessa S.; Silva, Fernando C.; Silva, Ademir X.; Alvarez, Gustavo B.

2011-01-01

Boron neutron capture therapy - BNCT - is a binary cancer treatment used in brain tumors. The tumor is loaded with a boron compound and subsequently irradiated by thermal neutrons. The therapy is based on the 10 B (n, α) 7 Li nuclear reaction, which emits two types of high-energy particles, α particle and the 7 Li nuclei. The total kinetic energy released in this nuclear reaction, when deposited in the tumor region, destroys the cancer cells. Since the success of the BNCT is linked to the different selectivity between the tumor and healthy tissue, it is necessary to carry out a sensitivity analysis to determinate the boron concentration. Computational simulations are very important in this context because they help in the treatment planning by calculating the lowest effective absorbed dose rate to reduce the damage to healthy tissue. The objective of this paper is to present a deterministic method based on generalized perturbation theory (GPT) to perform sensitivity analysis with respect to the 10 B concentration and to estimate the absorbed dose rate by patients undergoing this therapy. The advantage of the method is a significant reduction in computational time required to perform these calculations. To simulate the neutron flux in all brain regions, the method relies on a two-dimensional neutron transport equation whose spatial, angular and energy variables are discretized by the diamond difference method, the discrete ordinate method and multigroup formulation, respectively. The results obtained through GPT are consistent with those obtained using other methods, demonstrating the efficacy of the proposed method. (author)

Application of generalized perturbation theory to sensitivity analysis in boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Garcia, Vanessa S. [Universidade Federal Fluminense (EEIMVR/UFF-RJ), Volta Redonda, RJ (Brazil). Escola de Engenharia Industrial e Metalurgica. Programa de Pos-Graduacao em Modelagem Computacional em Ciencia e Tecnologia; Silva, Fernando C.; Silva, Ademir X., E-mail: fernando@con.ufrj.b, E-mail: ademir@con.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Alvarez, Gustavo B. [Universidade Federal Fluminense (EEIMVR/UFF-RJ), Volta Redonda, RJ (Brazil). Escola de Engenharia Industrial e Metalurgica. Dept. de Ciencias Exatas

2011-07-01

Boron neutron capture therapy - BNCT - is a binary cancer treatment used in brain tumors. The tumor is loaded with a boron compound and subsequently irradiated by thermal neutrons. The therapy is based on the {sup 10}B (n, {alpha}) {sup 7}Li nuclear reaction, which emits two types of high-energy particles, {alpha} particle and the {sup 7}Li nuclei. The total kinetic energy released in this nuclear reaction, when deposited in the tumor region, destroys the cancer cells. Since the success of the BNCT is linked to the different selectivity between the tumor and healthy tissue, it is necessary to carry out a sensitivity analysis to determinate the boron concentration. Computational simulations are very important in this context because they help in the treatment planning by calculating the lowest effective absorbed dose rate to reduce the damage to healthy tissue. The objective of this paper is to present a deterministic method based on generalized perturbation theory (GPT) to perform sensitivity analysis with respect to the {sup 10}B concentration and to estimate the absorbed dose rate by patients undergoing this therapy. The advantage of the method is a significant reduction in computational time required to perform these calculations. To simulate the neutron flux in all brain regions, the method relies on a two-dimensional neutron transport equation whose spatial, angular and energy variables are discretized by the diamond difference method, the discrete ordinate method and multigroup formulation, respectively. The results obtained through GPT are consistent with those obtained using other methods, demonstrating the efficacy of the proposed method. (author)

Sludge pasteurization and upgrading by radiation. Bilateral research cooperation between OAEP and JAERI

International Nuclear Information System (INIS)

1995-07-01

The research cooperation between office of Atomic Energy for Peace, Thailand (OAEP) and Japan Atomic Energy Research Institute (JAERI) on 'Sludge Pasteurization and Upgrading by Radiation' was carried out for 4 years starting from March 1990. This cooperation was performed through information exchange meetings (Steering Committee Meeting), held in Takasaki and Bangkok, and experiments and discussions by scientist exchange, Many useful results were obtained on radiation inactivation effect of pathogen and parasites, upgrading of irradiated sludges to fertilizer, animal feeds and biological pesticides. This report includes the main results of the research cooperation reported at the First to Fifth Steering Committee Meetings as the progress reports. (author)

Design of the JAERI Fuel Cleanup System for the Tritium Systems Test Assembly

International Nuclear Information System (INIS)

Konishi, Satoshi; Hayashi, Takumi; Naruse, Yuji; Okuno, Kenji; Carlson, R.V.; Anderson, J.L.

1993-03-01

TSTA is operated under the US-Japan collaboration program for the study of fusion fuel cycle technology. A plasma exhaust processing subsystem, JAERI Fuel Cleanup (JFCU) was fabricated in Japan, and installed at the TSTA as a major subsystem of the TSTA loop under the agreement. This process is based on some Japanese developed components, and designed to meet TSTA requirements by both parties. This document describes all the technical and safety features in accordance with the LANL QA format. The process has a capability to process simulated plasma exhaust at the flow rate of 15 mol/h, that is 1/5 for ITER. (author)

Characteristics of neutron irradiation facility and dose estimation method for neutron capture therapy at Kyoto University research reactor institute

International Nuclear Information System (INIS)

Kobayashi, T.; Sakurai, Y.; Kanda, K.

2001-01-01

The neutron irradiation characteristics of the Heavy Water Neutron Irradiation Facility (HWNIF) at the Kyoto University Research Reactor Institute (KIJRRI) for boron neutron capture therapy (BNCT), is described. The present method of dose measurement and its evaluation at the KURRI, is explained. Especially, the special feature and noticeable matters were expounded for the BNCT with craniotomy, which has been applied at present only in Japan. (author)

Proton linacs for boron neutron capture therapy

International Nuclear Information System (INIS)

Lennox, A.J.

1993-08-01

Recent advances in the ability to deliver boron-containing drugs to brain tumors have generated interest in ∼4 MeV linacs as sources of epithermal neutrons for radiation therapy. In addition, fast neutron therapy facilities have been studying methods to moderate their beams to take advantage of the high cross section for epithermal neutrons on boron-10. This paper describes the technical issues involved in each approach and presents the motivation for undertaking such studies using the Fermilab linac. the problems which must be solved before therapy can begin are outlined. Status of preparatory work and results of preliminary measurements are presented

Progress in study of a medical reactor for boron neutron capture therapy

International Nuclear Information System (INIS)

Sasaki, Makoto; Hirota, Jitsuya; Tamao, Shigeo; Kanda, Keiji; Mishima, Yutaka.

1993-01-01

A design study of a medical reactor for Boron Neutron Capture Therapy has made progress. Main specifications of the reactor are as follows; thermal power of 2 MW, water cooling by natural convection, semitight core of hexagonal lattice, UO 2 fuel rod of 9.5 mm diameter and no refueling in the reactor-life. Three horizontal and one vertical neutron beam holes are to be provided for simultaneous treatments by thermal and epithermal neutrons and for further biomedical research. The design objectives for the beam holes are to deliver the therapeutic doses in a modest time (30 to 60 min) with minimal fast neutron and gamma contaminants. The n-γ coupling Sn transport calculations have been carried out using n-21 and γ-9 group cross sections on 2-dim. practical models. The calculated results indicate that the design objectives will be achievable even if the thermal power of the reactor is reduced to 1 MW. (author)

ARGO, 1-D Neutron Diffusion in Slab, Cylindrical, Spherical Geometry from JAERI Fast-Set, ABBN, RCBN

International Nuclear Information System (INIS)

Ikawa, Koji

1971-01-01

1 - Nature of physical problem solved: ARGO is a one-dimensional (slab, cylinder or sphere), multigroup diffusion code for use in fast reactor criticality and kinetic parameter analysis. Three cross section sets, i.e., JAERI-Fast-Set, ABBN-Set and RCBN-Set, of 25 groups are prepared for the code as its library tapes. 2 - Method of solution: Eigenvalues are computed by ordinary source-iteration techniques with ordinary acceleration methods for convergence. 3 - Restrictions on the complexity of the problem: Sphere geometry

Primary study for boron neutron capture therapy uses the RSG-GAS beam tube facility

International Nuclear Information System (INIS)

Suroso

2000-01-01

The minimum epithermal neutron flux as one of the prerequisite of Boron Neutron Capture Therapy (BNCT) is 1.0 x 10 9 n/(cm 2 s) RSG-GAS have 6 beam tube facilities for neutron source, which is one of the beam tube S-2 has a possibility to utilization for BNCT facility. The totally flux neutron measurement in the front of S-2 beam tube is 1.8 x 10 7 n/(cm 2 s). The neutron flux measurement was less than for BNCT minimum prerequisite. Concerning to the flux neutron production in the reactor, which is reach to 2.5 x 10 14 n/(cm 2 s), there for the S-2 beam tube could be used beside collimator modification

Present status of reactor physics in the United States and Japan-I. 5. Development of the MVP Monte Carlo Code at JAERI

International Nuclear Information System (INIS)

Mori, T.; Okumura, K.; Nagaya, Y.

2001-01-01

neutrons was used as a source spectrum, and the source neutrons were assumed to be emitted uniformly in a sharp cone of 5.94x10 -4 sr taking account of the geometry of the collimator. The experimental arrangement, thickness of the test shields, measured neutron source spectrum, and peak fluxes of source neutrons per proton beam charge (μC) are given in Ref. 7. The calculated neutron spectra for 20-, 4-, and 100-cm thick iron shields are compared in Fig. 1 with the measured ones. Good agreement is obtained for thinner cases. For the 100-cm thick shield, on the other hand, the calculation gives higher fluxes by a factor of ∼2 compared with the measurement, although errors of both measured and calculated results are fairly large. This overestimation is quite similar to that by the MCNPX calculation using the same cross-section library. For coupled neutron, proton, and meson transport calculations by MVP, collision analysis routines using evaluated nuclear data in the ENDF-6 format and macroscopic transport routines based on the model of the NMTC/JAERI nucleon-meson transport code have been developed, and their benchmark tests have just started. To treat a higher-energy region where no evaluated nuclear data are available, we have started to implement the Bertini and the Jet AA Microscopic Transport models into the MVP code. The combined code, whose energy range is extended up to 200 GeV, is called JAERI High Energy Transport. To simulate the Feynman-α experiment, which is one of time domain noise analyses, some functions were added to the MVP code to make the analog Monte Carlo simulation. The number of neutrons from each fission event can be sampled from the distribution given by Terrell. Scatter, capture, fission, and absorption detectors are available. A periodic-time boundary condition is used to describe stationary neutron sources including neutrons from spontaneous fission whose number should be selected from Terrell's distribution at each event. The MVP code

Electron beam flue gas treatment. Research cooperation among JAERI, IAEA and INCT

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

The research co-operation is conducted among Japan Atomic Energy Research Institute (JAERI), International Atomic Energy Agency (IAEA) and Institute of Nuclear Chemistry and Technology in Poland (INCT) on Electron Beam Flue Gas Treatment from January 1993 to March 1997. The first phase of the cooperation was carried out for 3 years from January 1993 to March 1995. This cooperation was performed through information exchange meetings (Coordination Meetings), held in Takasaki and Warsaw, and experiments and discussions by exchange scientists. Many useful results were obtained on electron beam treatment of flue gas from coal-combustion heat generation plant in Kaweczyn within the frame work of the research co-operation. This report includes the main results of the tripartite research cooperation. (author)

Search for unknown isotopes using the TIARA-ISOL and the JAERI-ISOL

Energy Technology Data Exchange (ETDEWEB)

Asai, Masato [Nagoya Univ. (Japan). School of Engineering

1997-07-01

The new neutron-deficient isotopes {sup 127}Pr and {sup 125}Pr, and the new neutron-rich isotopes {sup 166}Tb, {sup 165}Gd and {sup 161}Sm were identified using the TIARA-ISOL with {sup 36}Ar + {sup 92,94}Mo reactions, and the gas-jet coupled JAERI-ISOL with a proton-induced fission of {sup 238}U, respectively. The element-selective oxidation technique was used to reduce large contamination from isobars and molecular ions with production cross sections about one or two orders of magnitude as large as those of the new isotopes. The good signal-to-noise ratios achieved in the present measurements were essential to observe and identify weak X/{gamma} rays from the new isotopes. (author)

Biodistribution, toxicity and efficacy of a boronated porphyrin for boron neutron capture therapy

International Nuclear Information System (INIS)

Miura, Michiko; Micca, P.; Fairchild, R.; Slatkin, D.; Gabel, D.

1992-01-01

Boron-containing porphyrins may be useful for boron neutron capture therapy (BNCT) in the treatment of brain tumors. Porphyrins have been shown to accumulate in tumor tissue and to be essentially excluded from normal brain. However, problems of toxicity may prevent some boron-containing porphyrins from being considered for BNCT. The authors have synthesized the boronated porphyrin 2,4-bis-vinyl-o-nidocarboranyl-deuteroporphyrin IX (VCDP). Preliminary studies in tumor-bearing mice showed considerable uptake of boron at a total dose of 150 μg/gbw with low mortality. They now report that a total dose to mice of ∼ 275 μg VCDP/gbw administered in multiple intraperitoneal (ip) injections can provide 40-50μg B per gram of tumor with acceptable toxicity. Toxicity experiments and a preliminary trial of BNCT in mice given such doses are also reported

Proceeding of the workshop on the results of the cooperative research between JAERI and CHESCIR concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system

Energy Technology Data Exchange (ETDEWEB)

Amano, Hikaru; Saito, Kimiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

This workshop was organized and sponsored by the Japan Atomic Energy Research Institute (JAERI) and Chernobyl Science and Technology Center for International Research (CHESCIR). JAERI and CHESCIR have conducted 8 years research cooperation from 1992 to 1999 concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system, focusing on the Chernobyl contaminated area. It contained 3 research subjects. Subject-1 initiated at 1992 and focused the study on measurements and evaluation of environmental external exposure after nuclear accident. Subject-2 initiated at 1992 and focused the study on the validation of assessment models in an environmental consequence assessment methodology for nuclear accidents. Subject-3 initiated at 1995 and focused on the study on migration of radionuclides released into terrestrial and aquatic environment after nuclear accidents. This workshop was held to summarize the research cooperation between JAERI and CHESCIR, and to discuss future research needs in this field. (author)

Boron neutron capture therapy as new treatment for clear cell sarcoma: Trial on different animal model

International Nuclear Information System (INIS)

Andoh, Tooru; Fujimoto, Takuya; Sudo, Tamotsu; Suzuki, Minoru; Sakurai, Yoshinori; Sakuma, Toshiko; Moritake, Hiroshi; Sugimoto, Tohru; Takeuchi, Tamotsu; Sonobe, Hiroshi; Epstein, Alan L.; Fukumori, Yoshinobu; Ono, Koji; Ichikawa, Hideki

2014-01-01

Clear cell sarcoma (CCS) is a rare malignant tumor with a poor prognosis. In our previous study, the tumor disappeared under boron neutron capture therapy (BNCT) on subcutaneously-transplanted CCS-bearing animals. In the present study, the tumor disappeared under this therapy on model mice intramuscularly implanted with three different human CCS cells. BNCT led to the suppression of tumor-growth in each of the different model mice, suggesting its potentiality as an alternative to, or integrative option for, the treatment of CCS. - Highlights: • BNCT with the use of L-BPA was applied for three human clear cell sarcoma (CCS) cell lines. • BNCT trial was performed on a newly established intramuscularly CCS-bearing animal model. • A significant decrease of the tumor-volume was seen by single BNCT with the use of L-BPA. • A multiple BNCT application would be required for controlling the growth of any residual tumors

The radiation biology of Boron Neutron Capture Therapy

International Nuclear Information System (INIS)

Coderre, J.A.

2003-01-01

Boron Neutron Capture Therapy (BNCT) produces a complex mixture of high and low-LET radiations in tissue. Using data on the biological effectiveness of these various dose components, derived primarily in small animals irradiated with thermal neutrons, it has been possible to express clinical BNCT doses in photon-equivalent units. The accuracy of these calculated doses in normal tissue and tumor will be reviewed. Clinical trials are underway at a number of centers. There are differences in the neutron beams at these centers, and differences in the details of the clinical protocols. Ideally, data from all centers using similar boron compounds and treatment protocols should be compared and combined, if appropriate, in a multi-institutional study in order to strengthen statistical analysis. An international dosimetry exchange is underway that will allow the physical doses from the various treatment centers to be quantitatively compared. As a first step towards the comparison of the clinical data, the normal brain tolerance data from the patients treated in the initial Brookhaven National Laboratory and the Harvard/MIT BNCT clinical trials have been compared. The data provide a good estimate of the normal brain tolerance for a somnolence syndrome endpoint, and provide guidance for setting normal brain tolerance limits in ongoing and future clinical trials. Escalation of the dose in BNCT can be accomplished by increasing the amount of the boron compound administered, increasing the duration of the neutron exposure, or both. The dose escalations that have been carried out to date at the various treatment centers will be compared and contrasted. Possible future clinical trials using BNCT in combination with other modalities will be discussed

Boron neutron capture therapy in cancer: past, present and future

Energy Technology Data Exchange (ETDEWEB)

Pisarev, Mario A.; Dagrosa, Maria Alejandra; Juvenal, Guilermo J. [National Atomic Energy Commission, Buenos Aires (Argentina). Div. of Nuclear Biochemistry; University of Buenos Aires (Argentina). School of Medicine. Dept. of Human Biochemistry

2007-07-15

Undifferentiated thyroid cancer (UTC) is a very aggressive tumor with no effective treatment, since it lacks iodine uptake and does not respond to radio or chemotherapy. The prognosis of these patients is bad, due to the rapid growth of the tumor and the early development of metastasis. Boron neutron capture therapy (BNCT) is based on the selective uptake of certain boron non-radioactive compounds by a tumor, and the subsequent irradiation of the area with an appropriate neutron beam. {sup 10}B is then activated to {sup 11}B, which will immediately decay releasing alpha particles and {sup 7}Li, of high linear energy transfer (LET) and limited reach. Clinical trials are being performed in patients with glioblastoma multiform and melanoma. We have explored its possible application to UTC. Our results demonstrated that a cell line of human UTC has a selective uptake of borophenylalanine (BPA) both in vitro and after transplantation to nude mice. Treatment of mice by BNCT led to a complete control of growth and cure of 100% of the animals. Moreover dogs with spontaneous UTC also have a selective uptake of BPA. At the present we are studying the biodistribution of BPA in patients with UTC before its application in humans. (author)

Shielding design study for the JAERI/KEK spallation neutron source

International Nuclear Information System (INIS)

Maekawa, Fujio; Teshigawara, Makoto; Konno, Chikara; Ikeda, Yujiro; Watanabe, Noboru

2001-01-01

Shielding design for the JAERI/KEK spallation neutron source was studied. Bulk shielding characteristics and optimization of a beam shutter were investigated by using Monte Carlo calculation code NMTC/JAM and MCNP with LA-150 neutron cross-section library. The following remarks were derived. (1) Neutron dose outside of the concrete shield at 6.6 m from the center is ∼10 μSv/hr regardless of angles with respect to the proton beam axis. The neutron dose can be reduced more than a factor of 30 by adding natural boron of 5 wt% in the concrete. (2) When a beam shutter position just outside the void vessel and the shutter length of 2 m are assumed, a shutter made of copper (1.7 m) with polyethylene (0.3 m) is the optimum in terms of shielding performance as well as cost merit. A shutter made of tungsten is not so effective. (3) Further studies are needed for optimization of beam shutter position. (author)

Dose prescription in boron neutron capture therapy

International Nuclear Information System (INIS)

Gupta, N.M.S.; Gahbauer, R.A.; Blue, T.E.; Wambersie, A.

1994-01-01

The purpose of this paper is to address some aspects of the many considerations that need to go into a dose prescription in boron neutron capture therapy (BNCT) for brain tumors; and to describe some methods to incorporate knowledge from animal studies and other experiments into the process of dose prescription. Previously, an algorithm to estimate the normal tissue tolerance to mixed high and low linear energy transfer radiations in BNCT was proposed. The authors have developed mathematical formulations and computational methods to represent this algorithm. Generalized models to fit the central axis dose rate components for an epithermal neutron field were also developed. These formulations and beam fitting models were programmed into spreadsheets to simulate two treatment techniques which are expected to be used in BNCT: a two-field bilateral scheme and a single-field treatment scheme. Parameters in these spreadsheets can be varied to represent the fractionation scheme used, the 10 B microdistribution in normal tissue, and the ratio of 10 B in tumor to normal tissue. Most of these factors have to be determined for a given neutron field and 10 B compound combination from large animal studies. The spreadsheets have been programmed to integrate all of the treatment-related information and calculate the location along the central axis where the normal tissue tolerance is exceeded first. This information is then used to compute the maximum treatment time allowable and the maximum tumor dose that may be delivered for a given BNCT treatment. The effect of different treatment variables on the treatment time and tumor dose has been shown to be very significant. It has also been shown that the location of D max shifts significantly, depending on some of the treatment variables-mainly the fractionation scheme used. These results further emphasize the fact that dose prescription in BNCT is very complicated and nonintuitive. 11 refs., 6 figs., 3 tabs

Gadolinium neutron capture therapy for brain tumors. Biological aspects

International Nuclear Information System (INIS)

Takagaki, Masao; Oda, Yoshifumi; Matsumoto, Masato; Kikuchi, Haruhiko; Kobayashi, Tooru; Kanda, Keiji; Ujeno, Yowri.

1994-01-01

This study investigated the tumoricidal effect of gadolinium neutron capture therapy (Gd-NCT) in in vitro and in vivo systems using Gd-DTPA. In in vitro study, a certain amount of Gd-DTPA, yielding 5000 ppm Gd-n, was added to human glioma cells, T98G, upon which thermal neutrons were exposed. After irradiation, the cells were incubated and the colonies were counted 10 days later. In in vivo study, Fisher-344 rats with experimentally induced gliosarcoma cells (9L) were exposed to thermal neutrons at a fluence rate of 3E+9/s for 1 h immediately after iv injection of Gd-DTPA. Two weeks after irradiation, brain samples were histologically examined. Tumor clearance of Gd-DTPA was also determined. In vitro analysis showed that a 1% survival level was obtained at 3.75E+12 (n/cm 2 ) for the Gd (+) medium and 2.50E+13 (n/cm 2 ) for the Gd (-) medium. In in vivo analysis, the concentration of Gd in 9L-rat brain tumor after iv injection of 0.2 mg/kg Gd-DTPA was found to be less than 100 ppm, but Gd-NCT on 9L-rat brain tumor administered with a ten-fold dose showed a substantial killing effect on tumor without serious injury to the normal brain structure. The killing effect of Gd-NCT was confirmed in in vitro and in vivo systems. (N.K.)

Stability of nuclei in peripheral collisions in the JAERI quantum molecular dynamics model

International Nuclear Information System (INIS)

Mancusi, Davide; Niita, Koji; Maruyama, Tomoyuki; Sihver, Lembit

2009-01-01

The JAERI quantum molecular dynamics (JQMD) model has been successfully used for a long time now to describe many different aspects of nuclear reactions in a unified way. In some cases, however, the JQMD model cannot produce consistent results: First, it lacks a fully relativistically covariant approach to the problem of molecular dynamics; second, the quantum-mechanical ground state of nuclei cannot be faithfully reproduced in a semiclassical framework. Therefore, we introduce R-JQMD, an improved version of JQMD that also features a new ground-state initialization algorithm for nuclei. We compare the structure of the two codes and discuss whether R-JQMD can be adjusted to improve JQMD's agreement with measured heavy-ion fragmentation cross sections

Health physics in JAERI, no.28

International Nuclear Information System (INIS)

1986-09-01

In the annual report No.28 (fiscal 1985) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. There were no occupational exposure exceeding the maximum permissible dose and no release of radioactive gaseous and liquid waste beyond the release limit specified according to the regulations. In the environment there were observed no abnormal radioactivity due to facilities. Technology development and research; Technology developments were made as in the previous years for improving the techniques and methods in monitoring of individuals, facilities and environment, radiation measurement instrumentation and also in waste management and decontamination. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and estimation of radiation dose due to low level waste disposal. For radiation dosimetry: portable apparatus for calibration of radioactive gas monitors, evaluation of β-ray depth dose distribution, and exposure analysis through an extended series of specific jobs at JRR-2. For body radioactivity: characteristic of JAERI phantom for an assessment of Pu in lung, transfer compartment in the internal dose evaluation method, and radiosensitivity of chromosomes of rabbit lymphocytes. For airborne radioactivity and estimation of radiation dose due to wastedisposal: sheltering effect of houses for radioactive effluent, tritium oxide permeability of membrance in protective appliances, conversion rate of low concentration tritium gas to tritiated water, computer code for calculation of radiation dose from very low-level radioactive waste disposal and safety demonstration tests of national disposal of very low-level radioactive solid waste. (J.P.N.)

Long-Term Nuclear Knowledge Management (NKM) on Nuclear Production of Hydrogen - A Case Study of the Japan Atomic Energy Research Institute (JAERI)

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki

2007-01-01

In Japan, so-called a formal nuclear policy; The Framework for Nuclear Energy Policy is built up by Japan Atomic Energy Commission at every 5-year, in which not only a conventional light water reactor (LWR) but also a fast breeder reactor (FBR), HTGR and a fusion reactor (FR) is referred as a prominent candidate of long-term (<100 years) nuclear energy source. The policy makers might have multi-purpose scenarios for a future of innovated nuclear energy systems through results of various discussions at their level. According to long-term nuclear knowledge management, the author made ex ante evaluation of HTGR known as the intellectual assets of JAERI 1, from the viewpoint of hypothetical benefits under conditions of substantial uncertainty. Nuclear knowledge management (NKM) is an integrated, systematic approach to identifying, managing and sharing an organization's nuclear knowledge, and enabling persons to create new nuclear knowledge collectively and thereby helping achieve the objectives. NKM identifies, optimizes, and actively manages intellectual assets either in the form of explicit knowledge held in intangible products or tacit knowledge possessed by individuals or communities in the nuclear fields. In the present study the authors wish not only to show the validity of long-term NKM as a key factor of HTGR but also to assess their hypothetical benefits through the year 2050 under conditions of substantial uncertainty. It should be stressed that those factors are important intellectual assets of JAERI developed to date. Additionally, in the Framework for Nuclear Energy Policy constructed up by the Japan Atomic Energy Commission, a LWR, a fast breeder reactor (FBR), a HTGR, and a fusion reactor (FR) are all defined as eligible and prominent candidates for long-term nuclear energy sources. In this sense, we estimate here a direct market creation of (1) hydrogen energy production and (2) electricity generation, by commercialized HTGR through the year 2050 with

Electrostatic design and beam transport for a folded tandem electrostatic quadrupole accelerator facility for accelerator-based boron neutron capture therapy.

Science.gov (United States)

Vento, V Thatar; Bergueiro, J; Cartelli, D; Valda, A A; Kreiner, A J

2011-12-01

Within the frame of an ongoing project to develop a folded Tandem-Electrostatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT), we discuss here the electrostatic design of the machine, including the accelerator tubes with electrostatic quadrupoles and the simulations for the transport and acceleration of a high intensity beam. Copyright © 2011 Elsevier Ltd. All rights reserved.

Proceedings of JAERI-JNC joint conference on nuclear safety research. March 7, 2003, Tokyo

International Nuclear Information System (INIS)

Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

2003-08-01

The JAERI-JNC Joint Conference on Nuclear Safety Research was held on March 7, 2003 in Tokyo with 188 participants, ahead of planned unification of JAERI and JNC in 2005. The objectives of the conference are to present recent results of safety research conducted in both institutes in accordance with the Five-Year Safety Research Plan by the Nuclear Safety Commission (NSC), and to reflect suggestions from the participants for future research program. Prof. Matsubara, Vice Chairperson of NSC, first presented a special lecture entitled 'Expectation on Future Nuclear Safety Research in Japan'. Twelve papers were then presented on the overview of research results and those of individual research activities in the fields of nuclear facilities, radioactive waste and environmental radioactivity. In the final session, a panel discussion was conducted with a title of 'Expectation on Future Nuclear Safety Research' chaired by Prof. Kimura, Chairperson of Special Committee on Nuclear Safety Research under NSC. Through the presentations and discussions, consensus has almost been obtained among participants for several key issues on safety research to be conducted by a unified new organization, such as giving priority to safety research as one of major missions, assurance of independence of safety research with the governmental funds, assurance of transparency of the planning process of safety research, separation and harmonization between safety research and developmental research, importance of maintaining fundamental research and research facilities, promotion of cooperation with relevant organizations considering the needs from industries, and importance of dissemination of research results and personnel training. The present report compiles the summaries of special lecture, papers, questions and comments, panel discussions, and OHPs presented in the conference. (author)

Progress of neutral beam R and D for plasma heating and current drive at JAERI

International Nuclear Information System (INIS)

Ohara, Y.

1995-01-01

Recent progress and future plans regarding development of a high power negative ion source at the Japan Atomic Energy Research Institute (JAERI) are described. The neutral beam injection system, which is expected to play an important role not only in plasma heating but also in the plasma current drive in the fusion reactor, requires a high power negative ion source which can produce negative deuterium ion beams with current of order 20A at energy above 1MeV. In order to realize such a high power negative ion beam, intensive research and development has been carried out at JAERI since 1984. The negative hydrogen ion beam current of 10A achieved in recent years almost equals the value required for the fusion reactor. With regard to the negative ion acceleration, a high current negative ion beam of 0.2A has been accelerated up to 350keV electrostatically. On the basis of this recent progress, two development plans have been initiated as an intermediate step towards the fusion reactor. One is to develop a 500keV, 10MW negative ion based neutral beam injection system for JT-60U to demonstrate the neutral beam current drive in a high density plasma. The other is to develop a 1MeV, 1A ion source to demonstrate high current negative ion acceleration up to 1MeV. On the basis of this research and development, an efficient and reactor relevant neutral beam injection system will be developed for an experimental fusion reactor such as the International Thermonuclear Experimental Reactor. ((orig.))

The Boron Neutron Capture Therapy (BNCT) Project at the TRIGA Reactor in Mainz, Germany

Energy Technology Data Exchange (ETDEWEB)

Hampel, G.; Grunewald, C.; Schutz, C.; Schmitz, T.; Kratz, J.V. [Nuclear Chemistry, University of Mainz, D-55099 Mainz (Germany); Brochhausen, C.; Kirkpatrick, J. [Department of Pathology, University of Mainz, D-55099 Mainz (Germany); Bortulussi, S.; Altieri, S. [Department of Nuclear and Theoretical Physics University of Pavia, Pavia (Italy); National Institute of Nuclear Physics (INFN) Pavia Section, Pavia (Italy); Kudejova, P. [Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universitaet Muenchen, D-85748 Garching (Germany); Appelman, K.; Moss, R. [Joint Research Centre (JRC) of the European Commission, NL-1755 ZG Petten (Netherlands); Bassler, N. [University of Aarhus, Norde Ringade, DK-8000, Aarhus C (Denmark); Blaickner, M.; Ziegner, M. [Molecular Medicine, Health and Environment Department, AIT Austrian Institute of Technology GmbH (Austria); Sharpe, P.; Palmans, H. [National Physical Laboratory, Teddington TW11 0LW, Middlesex (United Kingdom); Otto, G. [Department of Hepatobiliary, Pancreatic and Transplantation Surgery, University of Mainz, D-55099 Mainz (Germany)

2011-07-01

The thermal column of the TRIGA reactor in Mainz is being used very effectively for medical and biological applications. The BNCT (boron neutron capture therapy) project at the University of Mainz is focussed on the treatment of liver tumours, similar to the work performed in Pavia (Italy) a few years ago, where patients with liver metastases were treated by combining BNCT with auto-transplantation of the organ. Here, in Mainz, a preclinical trial has been started on patients suffering from liver metastases of colorectal carcinoma. In vitro experiments and the first animal tests have also been initiated to investigate radiobiological effects of radiation generated during BNCT. For both experiments and the treatment, a reliable dosimetry system is necessary. From work elsewhere, the use of alanine detectors appears to be an appropriate dosimetry technique. (author)

Drug delivery system design and development for boron neutron capture therapy on cancer treatment

International Nuclear Information System (INIS)

Sherlock Huang, Lin-Chiang; Hsieh, Wen-Yuan; Chen, Jiun-Yu; Huang, Su-Chin; Chen, Jen-Kun; Hsu, Ming-Hua

2014-01-01

We have already synthesized a boron-containing polymeric micellar drug delivery system for boron neutron capture therapy (BNCT). The synthesized diblock copolymer, boron-terminated copolymers (Bpin-PLA-PEOz), consisted of biodegradable poly(D,L-lactide) (PLA) block and water-soluble polyelectrolyte poly(2-ethyl-2-oxazoline) (PEOz) block, and a cap of pinacol boronate ester (Bpin). In this study, we have demonstrated that synthesized Bpin-PLA-PEOz micelle has great potential to be boron drug delivery system with preliminary evaluation of biocompatibility and boron content. - Highlights: • Herein, we have synthesized boron-modified diblock copolymer. • Bpin-PLA-PEOz, which will be served as new boron containing vehicle for transporting the boron drug. • This boron containing Bpin-PLA-PEOz micelle was low toxicity can be applied to drug delivery

JAERI thermal reactor standard code system for reactor design and analysis SRAC

International Nuclear Information System (INIS)

Tsuchihashi, Keichiro

1985-01-01

SRAC, JAERI thermal reactor standard code system for reactor design and analysis, developed in Japan Atomic Energy Research Institute, is for all types of thermal neutron nuclear design and analysis. The code system has undergone extensive verifications to confirm its functions, and has been used in core modification of the research reactor, detailed design of the multi-purpose high temperature gas reactor and analysis of the experiment with a critical assembly. In nuclear calculation with the code system, multi-group lattice calculation is first made with the libraries. Then, with the resultant homogeneous equivalent group constants, reactor core calculation is made. Described are the following: purpose and development of the code system, functions of the SRAC system, bench mark tests and usage state and future development. (Mori, K.)

Advanced dust monitoring system applied to new TRU handling facility of JAERI

International Nuclear Information System (INIS)

Yabuta, H.; Shigeta, Y.; Sawahata, K.; Hasegawa, K.

1993-01-01

In JAERI, a large, scale multipurpose facility is under construction, which consists of a TRU waste management testing installation, a solution fuel treatment installation and critical assemblies with uranium and/or plutonium solution fuel. The facility is also equipped with a lot of gloveboxes for handling and treatment of solution fuel and hot cells for research on reprocessing process. As there may be a relatively high potential of air contamination, it is important to monitor air contamination effectively and efficiently. An advanced dust monitoring system was introduced for convenience of handling and automatical measurement of filter papers, by developing a filter-holder with an IC memory and a radioactivity measuring device with an automatic filter-holder changing mechanism as a part of a centralized monitoring system with a computer

A study of nuclei far from stability by using the JAERI ISOL

International Nuclear Information System (INIS)

Ichikawa, Shin-ichi

1988-01-01

Since a mass separator was installed at the JAERI tandem accelerator facilities, a high-temperature ion source, a tape transport system, a radiation detection system and a data acquisition system have been constructed for online experiments. Although the ion source can ionize effectively alkali, alkaline-earth and rare-earth elements, further we have developed a new technique applying the favoured formation of monoxide ions of La and Ce to strengthen elemental selectivity. Taking advantage of the technique and heavy-ion fusion-nucleon evaporation reactions, we are studying nuclei in the light rare-earth region. So far, decays of odd-odd nuclei such as 122,124 , 126 La and 128,130 Pr have been studied, and the isotope 121 La has been newly identified with a half-life of 5.2 ± 0.2 s. (author)

Design study of superconducting coils for the fusion DEMO plant at JAERI

International Nuclear Information System (INIS)

Isono, T.; Koizumi, N.; Okuno, K.; Kurihara, R.; Nishio, S.; Tobita, K.

2006-01-01

A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb 3 Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb 3 Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb 3 Al winding

Preliminary calculation with code CONTEMPT-LT for spray cooling tests with JAERI model containment vessel

International Nuclear Information System (INIS)

Tanaka, Mitsugu

1978-01-01

LWR plants have a containment spray system to reduce the escape of radioactive material to the environment in a loss-of-coolant accident (LOCA) by washing out fission products, especially radioiodine, and condensing the steam to lower the pressure. For carrying out the containment spray tests, pressure and temperature behaviour of the JAERI Model Containment Vessel in spray cooling has been calculated with computer program CONTEMPT-LT. The following could be studied quantitatively: (1) pressure and temperature raise rates for steam addition rate and (2) pressure fall rate for spray flow rate and spray heat transfer efficiency. (auth.)

Biological Tests for Boron Neutron Capture Therapy Research at the TRIGA Mark II Reactor in Pavia

Energy Technology Data Exchange (ETDEWEB)

Protti, N.; Ballarini, F.; Bortolussi, S.; De Bari, A.; Stella, S.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Nuclear Physics National Institute (INFN), Pavia (Italy); Bruschi, P. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Bakeine, J.G.; Cansolino, L.; Clerici, A.M. [Laboratory of Experimental Surgery, Department of Surgery, University of Pavia, Pavia (Italy)

2011-07-01

The thermal column of the TRIGA Mark II reactor of the Pavia University is used as an irradiation facility to perform biological tests and irradiations of living systems for Boron Neutron Capture Therapy (BNCT) research. The suitability of the facility has been ensured by studying the neutron flux and the photon background in the irradiation chamber inside the thermal column. This characterization has been realized both by flux and dose measurements as well as by Monte Carlo simulations. The routine irradiations concern in vitro cells cultures and different tumor animal models to test the efficacy of the BNCT treatment. Some results about these experiments will be described. (author)

Practice of producing cement packages for sea dumping and their quality control in Tokai Research Establishment, JAERI

International Nuclear Information System (INIS)

Hattori, Yoshiro; Fujisaki, Setsuo; Usami, Jun; Morishita, Satoru; Komatsu, Shigeru

1980-07-01

The production of cement packages for the exploratory sea dumping has been carried out at Waste Disposal and Decontamination Section, Tokai Research Establishment, JAERI. And around 1,000 packages were completed until 1979. The production practice were conducted based on NEA guideline and domestic regulation. In order to meet the guideline and regulation, consistent quality control is necessary to the production procedure. This Report describes about the procedure and quality control that were practiced from 1977 to 1979 in Tokai Research Establishment. (author)

Construction plan of ion irradiation facility in JAERI

International Nuclear Information System (INIS)

Tanaka, Ryuichi

1987-01-01

The Takasaki Radiation Chemistry Research Establishment of Japan Atomic Energy Research Institute (JAERI) started the construction of an ion irradiation facility to apply ion beam to the research and development of radiation resistant materials for severe environment, the research on biotechnology and new functional materials. This project was planned as ion beam irradiation becomes an effective means for the research on fundamental physics and advanced technology, and the national guideline recently emphasizes the basic and pioneering field in research and development. This facility comprises an AVF cyclotron with an ECR ion source (maximum proton energy: 90 MeV), a 3 MV tandem accelerator, a 3 MV single end type Van de Graaf accelerator and a 400 kV ion implanter. In this report, the present status of planning the accelerators and the facility to be constructed, the outline of research plan, the features of the accelerators, and the beam characteristics are described. In this project, the research items are divided into the materials for space environment, the materials for nuclear fusion reactors, biotechnology, new functional materials, and ion beam technology. The ion beams required for the facility are microbeam, pulsed beam, multiple beam, neutron beam and an expanded irradiation field. (Kako, I.)

D-T neutron skyshine experiments at JAERI/FNS

Energy Technology Data Exchange (ETDEWEB)

Nishitani, Takeo; Ochiai, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yoshida, Shigeo [Tokai Univ., Hiratsuka, Kanagawa (JP)] (and others)

2003-03-01

The D-T neutron skyshine experiments have been carried out at the Fusion Neutronics Source (FNS) of JAERI with the neutron yield of {approx}1.7x10{sup 11} n/s. The concrete thickness of the roof and the wall of a FNS target room are 1.15 and 2 m, respectively. The FNS skyshine port with a size of 0.9x0.9 m{sup 2} was open during the experimental period. The radiation dose rate outside the target room was measured as far as about 550 m away from the D-T target point with a spherical rem-counter. The highest neutron dose was about 0.5 {mu}Sv/hr at a distance of 30 m from the D-T target point and the dose rate was attenuated to 0.002 {mu}Sv/hr at a distance of 550 m. The measured neutron dose distribution was analyzed with Monte Carlo code MCNP-4B and a simple line source model. The MCNP calculation overestimates the neutron dose in the distance range larger than 250 m. The neutron spectra were evaluated with a {sup 3}He detector with different thickness of polyethylene neutron moderators. Secondary gamma-rays were measured with high purity Ge detectors and NaI scintillation detectors. (author)

MCNP speed advances for boron neutron capture therapy

International Nuclear Information System (INIS)

Goorley, J.T.; McKinney, G.; Adams, K.; Estes, G.

1998-04-01

The Boron Neutron Capture Therapy (BNCT) treatment planning process of the Beth Israel Deaconess Medical Center-M.I.T team relies on MCNP to determine dose rates in the subject's head for various beam orientations. In this time consuming computational process, four or five potential beams are investigated. Of these, one or two final beams are selected and thoroughly evaluated. Recent advances greatly decreased the time needed to do these MCNP calculations. Two modifications to the new MCNP4B source code, lattice tally and tracking enhancements, reduced the wall-clock run times of a typical one million source neutrons run to one hour twenty five minutes on a 200 MHz Pentium Pro computer running Linux and using the GNU FORTRAN compiler. Previously these jobs used a special version of MCNP4AB created by Everett Redmond, which completed in two hours two minutes. In addition to this 30% speedup, the MCNP4B version was adapted for use with Parallel Virtual Machine (PVM) on personal computers running the Linux operating system. MCNP, using PVM, can be run on multiple computers simultaneously, offering a factor of speedup roughly the same as the number of computers used. With two 200 MHz Pentium Pro machines, the run time was reduced to forty five minutes, a 1.9 factor of improvement over the single Linux computer. While the time of a single run was greatly reduced, the advantages associated with PVM derive from using computational power not already used. Four possible beams, currently requiring four separate runs, could be run faster when each is individually run on a single machine under Windows NT, rather than using Linux and PVM to run one after another with each multiprocessed across four computers. It would be advantageous, however, to use PVM to distribute the final two beam orientations over four computers

Monte Carlo calculations of lung dose in ORNL phantom for boron neutron capture therapy

International Nuclear Information System (INIS)

Krstic, D.; Markovic, V.M.; Jovanovic, Z.; Milenkovic, B.; Nikezic, D.; Atanackovic, J.

2014-01-01

Monte Carlo simulations were performed to evaluate dose for possible treatment of cancers by boron neutron capture therapy (BNCT). The computational model of male Oak Ridge National Laboratory (ORNL) phantom was used to simulate tumours in the lung. Calculations have been performed by means of the MCNP5/X code. In this simulation, two opposite neutron beams were considered, in order to obtain uniform neutron flux distribution inside the lung. The obtained results indicate that the lung cancer could be treated by BNCT under the assumptions of calculations. The difference in evaluated dose in cancer and normal lung tissue suggests that BNCT could be applied for the treatment of cancers. The difference in exposure of cancer and healthy tissue can be observed, so the healthy tissue can be spared from damage. An absorbed dose ratio of metastatic tissue-to-the healthy tissue was ∼5. Absorbed dose to all other organs was low when compared with the lung dose. Absorbed dose depth distribution shows that BNC therapy can be very useful in the treatments for tumour. The ratio of the tumour absorbed dose and irradiated healthy tissue absorbed dose was also ∼5. It was seen that an elliptical neutron field was better irradiation choice. (authors)

Proceedings of the 7th symposium on JAERI's Reimei Research Program

International Nuclear Information System (INIS)

Shibata, Takemasa

2004-02-01

The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion Project of Japan Atomic Energy Research Institute. The objective of the system is to encourage often vague or unique ideas in the field of fundamental nuclear science and nuclear energy. The symposium on JAERI's Reimei Research Program carried out at the 2002 fiscal year was held at Tokai Research Establishment on 1st and 2nd of July 2003. Each report of 51 papers was carried out by short presentation and poster, and the active discussion was carried out by about 120 attendees. Those presented papers are compiled in the proceedings. We hope that many new researches grow and develop by the help of Reimei Research Promotion Project. The 36 of the presented papers are indexed individually. (J.P.N.)

Proceedings of the 8th symposium on JAERI's Reimei research program

International Nuclear Information System (INIS)

Shibata, Takemasa

2004-12-01

The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion Project of the Japan Atomic Energy Research Institute. The objective of the system is to encourage often vague and/or unique ideas in the field of fundamental nuclear science and nuclear energy. The symposium on JAERI's Reimei Research Program carried out in the 2003 fiscal year was held at Tokai Research Establishment on 29th and 30th of June 2004. 42 papers were reported through the short presentation followed by the poster presentation, and the active discussions was carried out by about 120 attendees. Those presented papers are compiled in the proceedings. We hope that new researches will be grown and developed by the help of Reimei Research Promotion Project. The 40 of the presented papers are indexed individually. (J.P.N.)

Proceedings of the 9th symposium on JAERI's Reimei Research Program

International Nuclear Information System (INIS)

Yamashita, Toshiyuki

2005-09-01

The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion project of the Japan Atomic Energy Research Institute. The objective of the program is to encourage original and/or unique ideas in the field of fundamental nuclear science and nuclear energy. The Symposium on JAERI's Reimei Research Program carried out in the 2004 fiscal year was held at Tokai Research Establishment on 28th and 29th of June 2005. 38 papers were reported through the short presentation followed by the poster presentation, and animated discussions were carried out by about 120 attendees. These presented papers were compiled in the proceedings. We hope that new researches will be grown and developed by the help of Reimei Research Promotion project. The 37 of the presented papers are indexed individually. (J.P.N.)

Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI's activities in the 1st Japanese-Korean-Russian joint expedition 1994

International Nuclear Information System (INIS)

Amano, Hikaru; Matsunaga, Takeshi; Yabuuchi, Noriaki.

1996-10-01

Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI's activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

Boron neutron capture therapy for recurrent head and neck malignancies

International Nuclear Information System (INIS)

Kato, Itsuro; Ono, Koji; Sakurai, Yoshinori

2006-01-01

To avoid severe impairment of oro-facial structures and functions, it is necessary to explore new treatments for recurrent head and neck malignancies (HNM). Boron neutron capture therapy (BNCT) is tumor-cell targeted radiotherapy that has significant superiority over conventional radiotherapies in principle. So far for 4 years and 3 months, we have treated with 37 times of BNCT for 21 patients (14 squamous cell carcinomas (SCC), 4 salivary gland carcinomas and 3 sarcomas) with a recurrent and far advanced HNM since 2001. Results are (1) 10 B concentration of tumor/normal tissue ratio (T/N ratio) of FBPA-PET studies were SCC: 1.8-5.7, sarcoma: 2.5-4.0, parotid tumor: 2.5-3.7. (2) Therapeutic effects were CR: 6cases, PR: 11cases, PD: 3cases NE (not evaluated): 1case. Response rate was 81%. (3) Improvement of QOL such as a relief of severe pain, bleeding, and exudates at the local lesion, improvement of PS, disappearance of ulceration, covered with normal skin and preserved oral and maxillofacial functions and tissues. (4) Survival periods after BNCT were 1-51 months (mean: 9.8 months). 4-year survival rate was 39% by Kaplan-Meier analysis. (5) A few adverse-effects such as transient mucositis, alopecia were recognized. These results indicate that BNCT represents a new and promising treatment approach for advanced HNM. (author)

Development of lithium target for accelerator based neutron capture therapy

International Nuclear Information System (INIS)

Taskaev, Sergey; Bayanov, Boris; Belov, Victor; Zhoorov, Eugene

2006-01-01

Pilot innovative accelerator based neutron source for neutron capture therapy of cancer is now of the threshold of its operation at the BINP, Russia. One of the main elements of the facility is lithium target producing neutrons via threshold 7 Li(p,n) 7 Be reaction at 25 kW proton beam with energies 1.915 MeV or 2.5 MeV. The main problems of lithium target were determined to be: 7 Be radioactive isotope activation keeping lithium layer solid, presence of photons due to proton inelastic scattering on lithium nuclei, and radiation blistering. The results of thermal test of target prototype were presented as previous NCT Congress. It becomes clear that water is preferable for cooling the target, and that lithium target 10 cm in diameter is able to run before melting. In the present report, the conception of optimal target is proposed: thin metal disk 10 cm in diameter easy for detaching, with evaporated thin layer of pure lithium from the side of proton beam exposure, its back being intensively cooled with turbulent water flow to maintain lithium layer solid. Design of the target for the neutron source constructed at BINP is shown. The results of investigation of radiation blistering and lithium layer are presented. Target unit of facility is under construction now, and obtaining neutrons is expected in nearest future. (author)

Boron neutron capture therapy for children with malignant brain tumor

International Nuclear Information System (INIS)

Nakagawa, Yoshinobu; Komatsu, Hisao; Kageji, Teruyoshi; Tsuji, Fumio; Matsumoto, Keizo; Kitamura, Katsuji; Hatanaka, Hiroshi; Minobe, Takashi.

1993-01-01

Among the 131 cases with brain tumors treated by boron-neutron capture therapy (BNCT), seventeen were children. Eight supratentorial tumors included five astrocytomas(grade 2-4), two primitive neuroectodermal tumors (PNET) and one rhabdomyosarcoma. Seven pontine tumors included one astrocytoma, one PNET and 5 unverified gliomas. Two cerebellar tumors (PNET and astrocytoma) were also treated. All pontine tumors showed remarkable decrease in size after BNCT. However, most of them showed regrowth of the tumors because the neutrons were insufficient due to the depth. Four cases with cerebral tumor died of remote cell dissemination, although they all responded to BNCT. One of them survived 7 years after repeated BNCTs. An 11 years old girl with a large astrocytoma in the right frontal lobe has lived more than 11 years and is now a draftswoman at a civil engineering company after graduating from a technical college. An 8 years old girl with an astrocytoma in the left occipital lobe has no recurrence of the tumor for 2 years and attends on elementary school without mental and physical problems. Two children (one year old girl and four years old boy) with cerebellar tumors have shown showed an excellent growth after BNCT and had no neurological deficits. Mental and physical development in patients treated by BNCT is usually better than that in patients treated by conventional radiotherapy. (author)

FURNACE-J, 2-D Diffusion Burnup for Fast Reactors from JAERI Fast-Set

International Nuclear Information System (INIS)

Ikawa, Koji

1984-01-01

1 - Nature of physical problem solved: FURNACEJ is a two-dimensional diffusion-burnup code for use in the detailed burnup analysis of fast reactors. The code is an extension code of the FURNACE. There exists no essential difference between FURNACE and FURNACEJ. However, the latter can deal with JAERI-Fast-Set as its cross section library, while the former is designed to use ABBN set. Additionally, in FURNACEJ, group-dependent and -independent transverse buckling of each region can be computed and punched on cards, if desired. This is prepared for users so as to use them as input data for detailed two-dimensional x-y calculations. 2 - Restrictions on the complexity of the problem: Only r-z geometry is available

Progress report on neutron scattering at JAERI

Energy Technology Data Exchange (ETDEWEB)

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

1998-10-01

In the first half of fiscal year 1997, JRR-3M was operated for 97 days followed by a long term shut down for its annual maintenance. Three days were lost out of 100 scheduled operation days, due to a trouble in irradiation facility. Neutron scattering research activities at the JRR-3M have been extended from that of fiscal year 1996. In the Research Group for Quantum Condensed Matter System, experimental study under high pressures, low temperatures and high fields as well as coupling of these conditions were planned to find new quantum condensed matter systems. And, obtained experimental results were immediately provided to theorists for their investigations. In cooperation with new group, Research Group for Neutron Scattering of Strongly Correlated Electron Systems and Research Group for Neutron Scattering at Ultralow Temperatures were carrying neutron scattering experiments at JRR-3M. Research Group for Neutron Crystallography in Biology had opened a way for investigating biomatter neutron diffraction research with high experimental accuracy by growing a millimeter-class large single crystal. In fiscal year 1997, 39 research projects were conducted by these four groups and other staffs in JAERI, 27 projects collaborated with university researchers and 3 projects collaborated with private enterprises were also conducted as complementary researches. 2117 days of machine times were requested to use 8 neutron scattering instruments this year, which corresponded to 1.51 times larger than those planned at its beginning. (G.K.)

Centralized environmental radiation monitoring system in JAERI

International Nuclear Information System (INIS)

Katagiri, H.; Kobalyashi, H.

1993-01-01

JAERI has continued the environmental radiation background survey and monitoring to ensure the safety of the peoples around the institute since one year before the first criticality of JRR-1 (Japan Research Reactor No.1) in August 1957. Air absorbed doses from β and γ radiation, α and β radioactivity in air and the radioactivities in environmental samples were the monitoring items. For the monitoring of β and γ radiation and α and β radioactivity in air, monitoring station and the centralized automatic environmental radiation monitoring system applying a computer were established as a new challenging monitoring system for nuclear facility, which was the first one not only in Japan but also in the would in 1960 and since then the system has been renewed two times (in 1973 and 1988) by introducing the latest technology in the fields of radiation detection and computer control at each stage. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop arisen from thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles

Centralized environmental radiation monitoring system in JAERI

International Nuclear Information System (INIS)

Katagiri, Hiroshi; Kobayashi, Hideo

1993-03-01

Japan Atomic Energy Research Institute (JAERI) has continued the radiation background survey and environmental radiation monitoring to ensure the safety of the residents around the Institute. For the monitoring of β and γ radiations and α and β radioactivities in air, the centralized automatic environmental radiation monitoring system (EMS) applying a computer with monitoring stations (MS) was established. The system has been renewed twice in 1973 and 1988. In 1962, a new concept emergency environmental γ-ray monitoring system (MP) was begun to construct and completed in 1965 independent of EMS. The first renewal of the EMS was carried out by focusing on the rapid and synthetic judgement and estimation of the environmental impacts caused by radiation and radioactive materials due to the operation of nuclear facilities by centralizing the data measured at MS, MP, a meteorological station, stack monitors and drainage monitoring stations under the control of computer. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop caused by thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min. monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles. (J.P.N.)

Acoustic emission measurement on large scale coils at JAERI

International Nuclear Information System (INIS)

Yoshida, K.; Hattori, Y.; Nishi, M.F.; Shimamoto, S.; Tsuji, H.

1986-01-01

The objective of acoustic emission measurement at Japan Atomic Energy Research Institute (JAERI) is an establishment of a general diagnostic method for superconducting magnet systems. Output of strain and displacement gages can not cover a whole system in monitoring premonitory phenomena of a magnet system s failure, because these sensors are mounted on points and therefore localized. Acoustic emissions can be transmitted to sensors through structural materials without electrical noise. Monitoring of acoustic emission will be one of the methods to predict a serious failure of magnet systems in a vacuum vessel. For this purpose, several sensors were installed on the Japanese LCT coil and the Test Module Coil (TMC). Some of acoustic activity was similar as seen in these coils. The correlation between voltage spikes and acoustic events is excellent during single coil charging mode, but poorer during out of plane force mode. There are no indicative acoustical phenomena before a magnet quench or during normal zone generation. The conditioning of acoustic events and voltage spikes can be seen after any cooling down. The localization of electrical insulation damage with the acoustic emission technique is one of its most useful applications

The heavy water accountancy for research reactors in JAERI

International Nuclear Information System (INIS)

Yoshijima, Tetsuo; Tanaka, Sumitoshi; Nemoto, Denjirou

1998-11-01

The three research reactors have been operated by the Department of Research Reactor and used about 41 tons heavy water as coolant, moderator and reflector of research reactors. The JRR-2 is a tank type research reactor of 10MW in thermal power and its is used as moderator, coolant and reflector about 16 tons heavy water. The JRR-3M is a light water cooled and moderated pool type research reactor with a thermal power of 20MW and its is used as reflector about 7.3 tons heavy water. In the JRR-4, which is a light water cooled swimming pool type research reactor with the maximum thermal power of 3.5MW, about 1 ton heavy water is used to supply fully thermalized neutrons with a neutron beam experiment of facility. The heavy water was imported from U.S.A., CANADA and Norway. Parts of heavy water is internationally controlled materials, therefore management of heavy water is necessary for materials accountancy. This report described the change of heavy water inventories in each research reactors, law and regulations for accounting of heavy water in JAERI. (author)

In vitro and in vivo studies in boron neutron capture therapy of malignant melanoma

International Nuclear Information System (INIS)

Allen, B.J.

1982-01-01

A multidisciplinary research project in boron neutron capture therapy of malignant melanoma is under consideration by the Australian Atomic Energy Commission. This paper reviews the biochemistry of melanoma and the properties of some melanoma-affined radiopharmaceuticals and their boron analogues. Human cell lines are being used for in vitro tests of uptake and incorporation of some of these compounds, and selected lines will then be implanted in nude mice for in vivo distribution studies. The fidelity of human melanoma xenografts in nude mice has been well studied, and results are reviewed in this paper. Boron concentration will be measured directly by plasma arc emission spectroscopy or liquid scintillation counting with 14 C-labelled boron analogues. Track-etch techniques will be used for the microscopic determination of boron in tumor sections. Neutron irradiation and radiobiology experiments are outlined

Clinical trials of boron neutron capture therapy [in humans] [at Beth Israel Deaconess Medical Center][at Brookhaven National Laboratory

International Nuclear Information System (INIS)

Wallace, Christine

2001-01-01

Assessment of research records of Boron Neutron Capture Therapy was conducted at Brookhaven National Laboratory and Beth Israel Deaconess Medical Center using the Code of Federal Regulations, FDA Regulations and Good Clinical Practice Guidelines. Clinical data were collected FR-om subjects' research charts, and differences in conduct of studies at both centers were examined. Records maintained at Brookhaven National Laboratory were not in compliance with regulatory standards. Beth Israel's records followed federal regulations. Deficiencies discovered at both sites are discussed in the reports

Accelerator conceptual design and needs of nuclear data for boron neutron capture therapy

International Nuclear Information System (INIS)

Sasaki, Makoto; Yamanaka, Toshiyuki; Yokobori, Hitoshi

1999-01-01

An optimization study has been made on an accelerator-based facility for the boron neutron capture therapy. The energy of the incident proton and the arrangement of the moderator assemblies are optimized. The beam current and the accelerating voltage are determined so that the accelerator power becomes minimum. The proposed facility is equipped with a 2.5 MeV proton accelerator of 10-25 mA, a lithium target, and a heavy water moderator contained in an aluminum tank. Each of these equipment is feasible, if proper R and D works have been done. Our new design requires the beam power of less than a hundred kW for the accelerator, although that of our previous design was 1 MW. The reduction of the beam power makes the cooling system for the target much simpler. The essential issues for realization of this concept are long-life lithium targets under high heat flux and high current proton accelerators with average currents of more than 10 mA. It is necessary for the reasonable design of a small-sized and low cost facility to get good accuracy nuclear reaction data. Especially, the latest Li/Be(p, n) neutron yield data in a range of threshold energy - few MeV are required for exact evaluation of neutron energy spectrum used therapy. And damage data by low energy proton beam are also important to evaluate integrity of target material. (author)

The specification and the operation characteristics of the low energy accelerator in JAERI-TRCRE

International Nuclear Information System (INIS)

Haruyama, Yasuyuki; Yotsumoto, Keiichi; Okamoto, Jiro

1993-06-01

The low energy accelerator system of JAERI TRCRE is of a non scanned type electron accelerator, manufactured by NISSIN HIGH VOLTAGE Co., LTD. The system consists of an oil filled d.c.high voltage generator, semicylindrical acceleration chamber in which a linear cathode is supported coaxially, and the products handling conveyor. The high voltage generator and the acceleration chamber are connected by a flexible cable. A batch irradiation can be carried out using the conveyor in inert gases. The output of the accelerator is 300 kV, 100 mA and the beam width is 60 cm. The specification, the operation procedure, and the operation characteristics of the system are described. (author)

Free-electron laser research-and-development and utilization program at Tokai, JAERI

International Nuclear Information System (INIS)

Kawarasaki, Yuuki

1992-01-01

The free-electron laser (FEL) research and development (R and D) and utilization program now underway at the Linac Laboratory, Tokai Research Establishment, JAERI, is presented together with the current status of the R and D. Specific feature of this program is at the points that the R and D period will range over a long time, around a decade, tentatively divided into three developmental phases, aiming at the final utilization in a field of nuclear energy industry and the FEL here under R and D is based on a superconducting (SC) linear accelerator (linac) which will in later phases be incorporated with addition of more SC-cavity modules for beam energy increase and with adoption of rather novel accelerator technique: beam recirculation both for further energy increase and for power economy by beam energy recovery. Application scheme is additionally discussed. (author)

Lattice design of 3 GeV synchrotron for JAERI-KEK joint project

Energy Technology Data Exchange (ETDEWEB)

Noda, F. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

This paper summarizes the Lattice of 3 GeV proton synchrotron for JAERI-KEK joint project. This 3 GeV ring provides 3 GeV proton beam for neutron science, muon science, exotic nuclear science facility and 50 GeV ring. The output beam power of this ring is 1 MW with 25 Hz operation. This beam power is a few times higher than that of the existing accelerators. To achieve this goal, it is important to cure an uncontrolled beam loss. A power of uncontrolled beam loss must be smaller than 1 W/m for hands-on maintenance. This uncontrolled beam loss is caused by beam injection, space-charge force, extraction and some known or unknown instability. The precise painting system, adequate aperture of ring and extraction line, and secure collimation systems are essential issues of this 3 GeV ring. (author)

Subcriticality of accelerator driven system by AESJ/JAERI working party

International Nuclear Information System (INIS)

Iwasaki, Tomohiko

2002-01-01

Under Atomic Energy Society of Japan (AESJ) and Japan Atomic Energy Research Institute (JAERI), a Working Party on Reactor Physics of Accelerator-Driven System (ADS-WP) has been set since March 1999 to review and investigate special subjects related to reactor physics research of Accelerator-Driven System (ADS). In the ADS-WP, the extensive and aggressive activity is being made by 25 professional members in the field of reactor physics in Japan. The ADS is now studying three subjects related to subcriticality of ADS; (1) calculation accuracy of subcriticality on ADS, (2) critical safety issues of ADS, and (3) theoretical review of subcriticality and its measurement methods. This paper describes two topics related to the subjects (1) and (2); one is an analysis of maximum reactivity potentially inserted to a subcritical core and the other is a benchmark proposal for checking calculation accuracy of subcriticality on ADS. The full specification of the calculation benchmark will be supplied by June 2002. Researchers from overseas, especially from Korea, are welcome to join this benchmark

Research and development of radiation utilizations in 1981 at JAERI

International Nuclear Information System (INIS)

1981-01-01

There is the field of radiation utilization such as the application of the effect of radiation on matters and the techniques of measurement and analysis utilizing the properties of radiation, in addition to the use of atomic energy as heat or electric power. The fields of application of radiation utilization are very wide, and are closely related to the health and daily life of people. The Japan Atomic Energy Research Institute has performed the research and development on radiation utilization regarding radiochemistry, the application of irradiation, and the production and industrial utilization of radioisotopes. Also, the research of the radiation resistance of organic materials used for nuclear facilities, the development of organic materials, and the production of tritium have become necessary. In this booklet, the recent results of radiation utilization in the JAERI are summarized. The research and development of ion exchange membranes, organic glasses, the fixation of living body activators and water paints, the techniques of utilizing irradiation, the techniques of radioisotope productions and utilization, and the techniques related to the development of atomic energy are reported. (Kako, I.)

The Effect of Deep Brain Stimulation Therapy on Fear-Related Capture of Attention in Parkinson's Disease and Essential Tremor: A Comparison to Healthy Individuals.

Science.gov (United States)

Camalier, Corrie R; McHugo, Maureen; Zald, David H; Neimat, Joseph S

2018-01-01

In addition to motor symptoms, Parkinson's disease (PD) involves significant non-motor sequelae, including disruptions in cognitive and emotional processing. Fear recognition appears to be affected both by the course of the disease and by a common interventional therapy, deep brain stimulation of the subthalamic nucleus (STN-DBS). Here, we examined if these effects extend to other aspects of emotional processing, such as attentional capture by negative emotional stimuli. Performance on an emotional attentional blink (EAB) paradigm, a common paradigm used to study emotional capture of attention, was examined in a cohort of individuals with PD, both on and off STN-DBS therapy (n=20). To contrast effects of healthy aging and other movement disorder and DBS targets, we also examined performance in a healthy elderly (n=20) and young (n=18) sample on the same task, and a sample diagnosed with Essential Tremor (ET) undergoing therapeutic deep brain stimulation of the ventral-intermediate nucleus (VIM-DBS, n=18). All four groups showed a robust attentional capture of emotional stimuli, irrespective of aging processes, movement disorder diagnosis, or stimulation. PD patients on average had overall worse performance, but this decrement in performance was not related to the emotional capture of attention. PD patients exhibited a robust EAB, indicating that the ability of emotion to direct attention remains intact in PD. Congruent with other recent data, these findings suggest that fear recognition deficits in PD may instead reflect a highly specific problem in recognition, rather than a general deficit in emotional processing of fearful stimuli.

Hemorrhage in mouse tumors induced by dodecaborate cluster lipids intended for boron neutron capture therapy

Directory of Open Access Journals (Sweden)

Schaffran T

2014-07-01

Full Text Available Tanja Schaffran,1 Nan Jiang,1 Markus Bergmann,2,3 Ekkehard Küstermann,4 Regine Süss,5 Rolf Schubert,5 Franz M Wagner,6 Doaa Awad,7 Detlef Gabel1,2,8 1Department of Chemistry, University of Bremen, 2Institute of Neuropathology, Klinikum Bremen-Mitte; 3Cooperative Center Medicine, University of Bremen, 4“In-vivo-MR” AG, FB2, University of Bremen, Bremen, 5Pharmaceutical Technology, University of Freiburg, Freiburg im Breisgau, 6Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II, Technische Unversitaet Muenchen, Garching, Germany; 7Department of Biochemistry, Alexandria University, Alexandria, Egypt; 8School of Engineering and Science, Jacobs University Bremen, Bremen, Germany Abstract: The potential of boron-containing lipids with three different structures, which were intended for use in boron neutron capture therapy, was investigated. All three types of boron lipids contained the anionic dodecaborate cluster as the headgroup. Their effects on two different tumor models in mice following intravenous injection were tested; for this, liposomes with boron lipid, distearoyl phosphatidylcholine, and cholesterol as helper lipids, and containing a polyethylene glycol lipid for steric protection, were administered intravenously into tumor-bearing mice (C3H mice for SCCVII squamous cell carcinoma and BALB/c mice for CT26/WT colon carcinoma. With the exception of one lipid (B-THF-14, the lipids were well tolerated, and no other animal was lost due to systemic toxicity. The lipid which led to death was not found to be much more toxic in cell culture than the other boron lipids. All of the lipids that were well tolerated showed hemorrhage in both tumor models within a few hours after administration. The hemorrhage could be seen by in vivo magnetic resonance and histology, and was found to occur within a few hours. The degree of hemorrhage depended on the amount of boron administered and on the tumor model. The observed unwanted effect of the lipids

Boron Neutron Capture Therapy at European research reactors - Status and perspectives

International Nuclear Information System (INIS)

Moss, R.L.

2004-01-01

Over the last decade. there has been a significant revival in the development of Boron Neutron Capture Therapy (BNCT) as a treatment modality for curing cancerous tumours, especially glioblastoma multiforme and subcutaneous malignant melanoma. In 1987 a European Collaboration on BNCT was formed, with the prime task to identify suitable research reactors in Europe where BNCT could be applied. Due to reasons discussed in this paper, the HFR Petten was chosen as the test-bed for demonstrating BNCT. Currently, the European Collaboration is approaching the start of clinical trials, using epithermal neutrons and borocaptate sodium (BSH) as the 10 B delivery agent. The treatment is planned to start in the first half of 1996. The paper here presents an overview on the principle of BNCT, the requirements imposed on a research reactor in order to be considered for BNCT, and the perspectives for other European materials testing reactors. A brief summary on the current status of the work at Petten is given, including: the design, construction and characterisation of the epithermal neutron beam: performance and results of the healthy tissue tolerance study; the development of a treatment planning programme based on the Monte Carlo code MCNP; the design of an irradiation room; and on the clinical trials themselves. (author)

Early effects of boron neutron capture therapy on rat glioma models

International Nuclear Information System (INIS)

Nakagawa, N.; Akai, F.; Fukawa, N.; Taneda, M.; Ono, K.; Suzuki, M.

2006-01-01

Early effects of boron neutron capture therapy on malignant gliomas are characterized by reduction of the enhanced area regression of the peritumoral edema radiologically. The aim of this study is to investigate the early histological changes of tumors and inflammatory cells after BNCT in the rat brain. The rats were treated with BNCT using boronophenyialanine (BPA) 7 days after implantation of C6 glioma cells. The tumors were assessed their sizes and configurations with magnetic resonance imaging, then killed 4 days after BNCT. The mean tumor volumes were 39mm 3 in BNCT-treated group, and 138 mm 3 in the control group. In the histological examination, tumors of the BNCT group showed less pleomorphic appearance with atypical nuclei and mitotic figures, compared with the control group. Necrosis and edematous changes in the neuropile were negligible. There existed remnant tumors adjacent to the lateral ventricle. The reactions of the inflammatory cells were examined with ED-1 of macrophage marker. ED-1 positive cells and their processes were reduced in the marginal area of tumor in the BNCT group. BNCT reduce the tumor progression by suppression of the proliferation. Inhibition of the activated macrophages may reduce peritumoral edema in early phase. (author)

Development of reference problems for neutron capture therapy treatment planning systems

International Nuclear Information System (INIS)

Albritton, J.R.; Kiger, W.S. III

2006-01-01

Currently, 5 different treatment planning systems (TPSs) are or have been used in clinical trials of Neutron Capture Therapy (NCT): MacNCTPlan, NCTPlan, BNCT Rtpe, SERA, and JCDS. This paper describes work performed to comprehensively test and compare 4 of these NCT treatment planning systems in order to facilitate the pooling of patient data from the different clinical sites for analysis of the clinical results as well as to provide an important quality assurance tool for existing and future TPSs. Two different phantoms were used to evaluate the planning systems: the modified Snyder head phantom and a large water-filled box, similar to that used in the International Dosimetry Exchange for NCT. The comparison of the resulting dose profile, isodose contours, and dose volume histograms to reference calculations performed with the Monte Carlo radiation transport code MCNP5 yielded many interesting differences. Each of the planning systems deviated from the reference calculations, with the newer systems (i.e., SERA and NCTPlan) most often yielding better agreement than their predecessors (i.e., BNCT Rtpe and MacNCTPlan). The combination of simple phantoms and sources with more complicated and realistic planning conditions has produced a well-rounded and useful suite of test problems for NCT treatment planning system analysis. (author)

Development of high intensity ion sources for a Tandem-Electrostatic-Quadrupole facility for Accelerator-Based Boron Neutron Capture Therapy

International Nuclear Information System (INIS)

Bergueiro, J.; Igarzabal, M.; Suarez Sandin, J.C.; Somacal, H.R.; Thatar Vento, V.; Huck, H.; Valda, A.A.; Repetto, M.

2011-01-01

Several ion sources have been developed and an ion source test stand has been mounted for the first stage of a Tandem-Electrostatic-Quadrupole facility For Accelerator-Based Boron Neutron Capture Therapy. A first source, designed, fabricated and tested is a dual chamber, filament driven and magnetically compressed volume plasma proton ion source. A 4 mA beam has been accelerated and transported into the suppressed Faraday cup. Extensive simulations of the sources have been performed using both 2D and 3D self-consistent codes.

Development of high intensity ion sources for a Tandem-Electrostatic-Quadrupole facility for Accelerator-Based Boron Neutron Capture Therapy

Energy Technology Data Exchange (ETDEWEB)

Bergueiro, J. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina)] [CONICET, Buenos Aires (Argentina); Igarzabal, M.; Suarez Sandin, J.C. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina); Somacal, H.R. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin (Argentina); Thatar Vento, V. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina)] [CONICET, Buenos Aires (Argentina); Huck, H.; Valda, A.A. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin (Argentina); Repetto, M. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica (Argentina)

2011-12-15

Several ion sources have been developed and an ion source test stand has been mounted for the first stage of a Tandem-Electrostatic-Quadrupole facility For Accelerator-Based Boron Neutron Capture Therapy. A first source, designed, fabricated and tested is a dual chamber, filament driven and magnetically compressed volume plasma proton ion source. A 4 mA beam has been accelerated and transported into the suppressed Faraday cup. Extensive simulations of the sources have been performed using both 2D and 3D self-consistent codes.

Boron neutron capture therapy (BNCT) for glioblastoma multiforme using the epithermal neutron beam at the Brookhaven Medical Research Reactor

International Nuclear Information System (INIS)

Capala, J.; Diaz, A.Z.; Chadha, M.

1997-01-01

The abstract describes evaluation of boron neutron capture therapy (BNCT) for two groups of glioblastoma multiforme patients. From September 1994 to February 1996 15 patients have been treated. In September 1997 another 34 patients were examined. Authors determined a safe starting dose for BNCT using epithermal neutrons and BPA-F. They have also evaluated adverse effects of BNCT at this starting dose. Therapeutic effectiveness of this starting dose has been evaluated. No significant side effects from BPA-F infusion or BNCT treatment were observed in normal brains

Boron neutron capture therapy (BNCT) for glioblastoma multiforme using the epithermal neutron beam at the Brookhaven Medical Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Capala, J. [Brookhaven National Lab., Upton, NY (United States); Diaz, A.Z.; Chadha, M. [Univ. Hospital, State Univ. of New York, NY (United States)] [and others

1997-12-31

The abstract describes evaluation of boron neutron capture therapy (BNCT) for two groups of glioblastoma multiforme patients. From September 1994 to February 1996 15 patients have been treated. In September 1997 another 34 patients were examined. Authors determined a safe starting dose for BNCT using epithermal neutrons and BPA-F. They have also evaluated adverse effects of BNCT at this starting dose. Therapeutic effectiveness of this starting dose has been evaluated. No significant side effects from BPA-F infusion or BNCT treatment were observed in normal brains.

Study on high speed lithium jet for neutron source of boron neutron capture therapy (BNCT)

International Nuclear Information System (INIS)

Takahashi, Minoru; Kobayashi, Tooru; Zhang, Mingguang; Mak, Michael; Stefanica, Jiri; Dostal, Vaclav; Zhao Wei

2012-01-01

The feasibility study of a liquid lithium type proton beam target was performed for the neutron source of the boron neutron capture therapy (BNCT). As the candidates of the liquid lithium target, a thin sheet jet and a thin film flow on a concave wall were chosen, and a lithium flow experiment was conducted to investigate the hydrodynamic stability of the targets. The surfaces of the jets and film flows with a thickness of 0.5 mm and a width of 50 mm were observed by means of photography. It has been found that a stable sheet jet and a stable film flow on a concave wall can be formed up to certain velocities by using a straight nozzle and a curved nozzle with the concave wall, respectively. (author)

Clinical potential of boron neutron capture therapy for locally recurrent inoperable previously irradiated head and neck cancer

International Nuclear Information System (INIS)

Lim, Diana; Quah, Daniel SC; Leech, Michelle; Marignol, Laure

2015-01-01

This review compares the safety and efficacy of boron neutron capture therapy (BNCT) in the treatment of previously irradiated, inoperable locoregional recurrent HNC patients and compares BNCT against the standard treatment of platinum-based chemotherapy. Our analysis of published clinical trials highlights efficacy of BNCT associated with mild side effects. However, the use of BNCT should be explored in stratified randomised trials. - Highlights: • BNCT can prolong median overall survival. • BNCT can be associated with severe adverse effects. • BNCT may be comparable to chemotherapy-based regimens. • BNCT may be comparable to re-irradiation techniques regimens in patients with low performance status.

Experiences in monitoring airborne radioactive contamination in JAERI

International Nuclear Information System (INIS)

Ikezawa, Y.; Okamoto, T.; Yabe, A.

1980-01-01

The following results were obtained at the Japan Atomic Energy Research Institute (JAERI) from experience in air monitoring at the hot cells for handling highly radioactive materials, the glove box containing plutonium and the cell for producing 99 Mo. (1) The ratios of activities of airborne dust to those of whole dust were of the order of 10 -2 for the semi-volatile form of 125 Sb, and 10 -3 to 10 -4 for the particulate form of 137 Cs, 144 Ce and 144 Pr, when irradiated fuels were cut in the hot cells. (2) The activity median aerodynamic diameter (AMAD) of airborne particle size distributions varied from O.4 to 15 μm with changing geometric standard deviation (sigmasub(g)) 1.7 to 7, depending on types of metallurgical treatment of fuels and on kinds of work in the cells. (3) A resuspension factor (the ratio of the concentration of airborne contamination to the surface contamination) was found to be 4x10 -8 to approximately 2x10 -7 cm -1 for plutonium oxide deposited on the floor surface. (4) The collection efficiency of the charcoal-loaded filter paper for airborne radioiodine, consisting of 60% inorganic and 40% organic iodide, was over 95% under conditions of relative humidity 40 to approximately 80% and face velocity 50 cm/sec, during the production of 99 Mo. (H.K.)

A theoretical model for the production of Ac-225 for cancer therapy by neutron capture transmutation of Ra-226.

Science.gov (United States)

Melville, G; Melville, P

2013-02-01

Radium needles that were once implanted into tumours as a cancer treatment are now obsolete and constitute a radioactive waste problem, as their half-life is 1600 years. We are investigating the reduction of radium by transmutation by bombarding Ra-226 with high-energy neutrons from a neutron source to produce Ra-225 and hence Ac-225, which can be used as a generator to produce Bi-213 for use in 'Targeted Alpha Therapy' for cancer. This paper examines the possibility of producing Ac-225 by neutron capture using a theoretical model in which neutron energy is convoluted with the corresponding neutron cross sections of Ra-226. The total integrated yield can then be obtained. This study shows that an intense beam of high-energy neutrons could initiate neutron capture on Ra-226 to produce Ra-225 and hence practical amounts of Ac-225 and a useful reduction of Ra-226. Copyright © 2012 Elsevier Ltd. All rights reserved.

MODELING THE RADIATION SHIELDING OF BORON NEUTRON CAPTURE THERAPY BASED ON 2.4 MEV D-D NEUTRON GENERATOR FACILITY

Directory of Open Access Journals (Sweden)

Muhammad Mu’Alim

2018-01-01

PEMODELAN PERISAI RADIASI PADA FASILITAS BORON NEUTRON CAPTURE THERAPY BERBASIS GENERATOR NEUTRON D-D 2,4 MeV. Telah dimodelkan perisai radiasi pada fasilitas Boron Neutron Capture Therapy (BNCT berbasis reaksi D-D pada Neutron Generator 2,4 MeV dengan Beam Shaping Assembly (BSA yang telah didesain sebelumnya. Pemodelan ini dilakukan untuk memperoleh suatu desain perisai radiasi untuk fasilitas BNCT berbasis generator neutron 2,4 MeV. Pemodelan dilakukan dengan cara memvariasikan bahan dan ketebalan perisasi radiasi. Bahan yang dipilih adalah beton barit, parafin, polietilen terborasi dan timbal. Perhitungan dilakukan menggunakan program MCNPX dengan tally F4 untuk menentukan laju dosis yang keluar dari perisai radiasi. Desain periasi radiasi dinyatakan optimal jika radiasi yang dihasilkan diluar perisai radiasi tidak melebihi Nilai Batas Dosis (NBD yang telah ditentukan oleh BAPETEN. Hasilnya, diperoleh suatu desain perisai radiasi menggunakan lapisan utama beton barit setebal 100 cm yang mengelilingi ruangan 100 cm x 100 cm x 166,4 cm dan polietilen terborasi 40 cm yang mengelilingi bahan beton barit. Kemudian ditambahkan beton barit 10 cm dan polietilen terborasi 10 cm untuk mengurangi radiasi primer yang lurus dari BSA setelah keluar dari lapisan utama. Laju dosis terbesar adalah 4,58 μSv·jam-1 pada sel 227 dan laju dosis rata-rata yang dihasilkan adalah sebesar 0,65 µSv·jam-1. Nilai laju dosis tersebut masih dibawah ambang batas NBD yang diperbolehkan oleh BAPETEN untuk pekerja radiasi. Kata kunci: Perisai radiasi, tally, laju dosis radiasi, BSA, BNCT

Molecular Medicine: Synthesis and In Vivo Detection of Agents for use in Boron Neutron Capture Therapy. Final Report

Energy Technology Data Exchange (ETDEWEB)

Kabalka, G. W.

2005-06-28

The primary objective of the project was the development of in vivo methods for the detection and evaluation of tumors in humans. The project was focused on utilizing positron emission tomography (PET) to monitor the distribution and pharamacokinetics of a current boron neutron capture therapy (BNCT) agent, p-boronophenylalanine (BPA) by labeling it with a fluorine-18, a positron emitting isotope. The PET data was then used to develop enhanced treatment planning protocols. The study also involved the synthesis of new tumor selective BNCTagents that could be labeled with radioactive nuclides for the in vivo detection of boron.

Molecular Medicine: Synthesis and In Vivo Detection of Agents for use in Boron Neutron Capture Therapy. Final Report

International Nuclear Information System (INIS)

Kabalka, G. W.

2005-01-01

The primary objective of the project was the development of in vivo methods for the detection and evaluation of tumors in humans. The project was focused on utilizing positron emission tomography (PET) to monitor the distribution and pharmacokinetics of a current boron neutron capture therapy (BNCT) agent, p-boronophenylalanine (BPA) by labeling it with a fluorine-18, a positron emitting isotope. The PET data was then used to develop enhanced treatment planning protocols. The study also involved the synthesis of new tumor selective BNCT agents that could be labeled with radioactive nuclides for the in vivo detection of boron

Development and in vitro testing of liposomal gadolinium-formulations for neutron capture therapy of glioblastoma multiforme

International Nuclear Information System (INIS)

Peters, Tanja

2013-01-01

For the improvement of current neutron capture therapy, several liposomal formulations of neutron capture agent gadolinium were developed and tested in a glioma cell model. Formulations were analyzed regarding physicochemical and biological parameters, such as size, zeta potential, uptake into cancer cells and performance under neutron irradiation. The neutron and photon dose derived from intracellular as well as extracellular Gd was calculated via Monte Carlo simulations and set in correlation with the reduction of cell survival after irradiation. To investigate the suitability of Gd as a radiosensitizer for photon radiation, cells were also irradiated with synchrotron radiation in addition to clinically used photons generated by linear accelerator. Irradiation with neutrons led to significantly lower survival for Gd-liposome-treated F98 and LN229 cells, compared to irradiated control cells and cells treated with non-liposomal Gd-DTPA. Correlation between Gd-content and -dose and respective cell survival displayed proportional relationship for most of the applied formulations. Photon irradiation experiments showed the proof-of-principle for the radiosensitizer approach, although the photon spectra currently used have to be optimized for higher efficiency of the radiosensitizer. In conclusion, the newly developed Gd-liposomes show great potential for the improvement of radiation treatment options for highly malignant glioblastoma.

Levels of tritium concentration in the environmental samples around JAERI TOKAI

International Nuclear Information System (INIS)

Matsuura, K.; Sasa, Y.; Nakamura, C.; Katagiri, H.

1995-01-01

By the operation of research reactors, tritium-handling facilities, nuclear power plants, and a reprocessing facility around JAERI TOKAI, tritium is released into the environment in compliance with the regulatory standards. To investigate the levels of tritium concentration in environmental samples around JAERI, rain, air (vapor and hydrogen gas), and tissue-free water of pine needles were measured and analyzed from 1984 to 1993. Sampling locations were determined by taking into consideration wind direction, distance from nuclear facilities, and population distribution. The NAKA site (about 6 km west-northwest from the Tokai site) was also selected as a reference point. Rain and tissue-free water of pine needles were sampled monthly. For air samples, sampling was carried out for two weeks by using the continuous tritium sampler. After the pretreatment of samples, tritium concentrations were measured by a low background liquid scintillation counter (detection limit 0.8 Bq/l). Annual mean tritium concentrations in rain observed at six points for 10 years was 0.8 to 8.9 Bq/l, which decreased with distance from the nuclear facilities. Tritium concentrations in rain obtained at Chiba City were around 0.8 Bq/l (1987-1988) and those at the NAKA site were 0.8 to 3.8 Bq/l. Annual mean HTO concentrations in air at three points for 10 years were 9.2 x 10 -2 to 1.1 Bq/m 3 , although HT concentrations in air, ranging from 1.7 x 10 -2 to 5.8 x 10 -2 Bq/m 3 , were not influenced by the operation of the nuclear facilities. Annual mean tritium concentrations in tissue-free water of pine needles at four points for 10 years were 1.4 to 31 Bq/l. Those at the NAKA site ranging from 1.4 to 6.2 Bq/l were in good agreement with the reported value by Takashima of 0.78 to 3.0 Bq/l at twenty-one locations in Japan. Monthly mean HTO concentrations in air for 10 years showed a good correlation with absolute humidity, while other samples showed no seasonal variation. Higher level tritium

Boron analysis for neutron capture therapy using particle-induced gamma-ray emission

International Nuclear Information System (INIS)

Nakai, Kei; Yamamoto, Yohei; Okamoto, Emiko; Yamamoto, Tetsuya; Yoshida, Fumiyo; Matsumura, Akira; Yamada, Naoto; Kitamura, Akane; Koka, Masashi; Satoh, Takahiro

2015-01-01

The neutron source of BNCT is currently changing from reactor to accelerator, but peripheral facilities such as a dose-planning system and blood boron analysis have still not been established. To evaluate the potential application of particle-induced gamma-ray emission (PIGE) for boron measurement in clinical boron neutron capture therapy, boronophenylalanine dissolved within a cell culture medium was measured using PIGE. PIGE detected 18 μgB/mL f-BPA in the culture medium, and all measurements of any given sample were taken within 20 min. Two hours of f-BPA exposure was required to create a boron distribution image. However, even though boron remained in the cells, the boron on the cell membrane could not be distinguished from the boron in the cytoplasm. - Highlights: • PIGE was evaluated for measuring blood boron concentration during clinical BNCT. • PIGE detected 18 μgB/mL f-BPA in culture medium. • All measurements of any given sample were taken within 20 min. • Two hours of f-BPA exposure is required to create boron distribution image by PIGE. • Boron on the cell membrane could not be distinguished from boron in the cytoplasm.

Cylindrical core reflood test facility (CCTF) and slab core reflood test facility (SCTF) for Japan Atomic Energy Research Institute (JAERI)

International Nuclear Information System (INIS)

1981-01-01

IHI has designed and constructed the CCTF at JAERI to be used in the safety analysis research on the loss of coolant accident in a PWR plant. This test facility is planned so that reflood phenomenon in the PWR plant (a phenomenon is that the bared and overheated core is reflooded by the emergency core cooling system when the coolant loss accident occurred) is simulated under various test conditions. The CCTF is the largest-scale test plant in the world, composed of approximately 2000 simulated fuel rods (electric heaters), 1 simulated pressure vessel, 4 primary cooling loops, 2 simulated steam generators, emergency core cooling system, and so on. The test conditions are controlled, and the test steps are sequentially progressed by the computing system, and test data are collected by the data acquisition system. Furthermore, IHI is now designing and constructing the SCTF in accordance with the JAERI research plan. The SCTF is similar to the CCTF in scale. Main feature of the SCTF is the form of the simulated core and the simulated pressure vessel, which is of slab construction to be representative of the radial section of the PWR reactor. Reliable and various data for safety analysis are expected by the CCTF and the SCTF. (author)

Dosimetry and stability studies of the boron neutron capture therapy agent F-BPA-Fr using PET and MRI

Science.gov (United States)

Dyke, Jonathan Paul

The treatment of deep seated brain tumors such as glioblastoma Multiforme has been unsuccessful for many patients. Surgical debulking, chemotherapy and standard radiotherapy have met with limited success. Boron neutron capture therapy offers a binary mode brachytherapy based on the following capture reaction that may provide an innovative alternative to standard forms of treatment:10B + n /to/ 11B /to 7Li + 4He + 2.31 MeVBoron is chemically attached to a tumor binding compound creating a non-toxic neutron absorber. A dose of epithermal neutrons provides the catalyst to produce the lithium and alpha particles which destroy any tissue within a length of one cell diameter from the boron compound. This dissertation uses 19F-MRI and 18F-PET to provide answers to the localization and biodistribution questions that arise in such a treatment modality. Practical patient dosimetry and actual treatment planning using the PET data is also examined. Finally, theoretical work done in the areas of compartmental modelling dealing with pharmacokinetic uptake of the PET radiotracer and dose analysis in microdosimetry is also presented.

Boron neutron capture therapy of intracerebral rat gliosarcomas

International Nuclear Information System (INIS)

Joel, D.D.; Fairchild, R.G.; Laissue, J.A.; Saraf, S.K.; Kalef-Ezra, J.A.; Slatkin, D.N.

1990-01-01

The efficacy of boron neutron capture therapy (BNCT) for the treatment of intracerebrally implanted rat gliosarcomas was tested. Preferential accumulation of 10B in tumors was achieved by continuous infusion of the sulfhydryl borane dimer, Na4(10)B24H22S2, at a rate of 45-50 micrograms of 10B per g of body weight per day from day 11 to day 14 after tumor initiation (day 0). This infusion schedule resulted in average blood 10B concentrations of 35 micrograms/ml in a group of 12 gliosarcoma-bearing rats and 45 micrograms/ml in a group of 10 similar gliosarcoma-bearing rats treated by BNCT. Estimated tumor 10B levels in these two groups were 26 and 34 micrograms/g, respectively. On day 14, boron-treated and non-boron-treated rats were exposed to 5.0 or 7.5 MW.min of radiation from the Brookhaven Medical Research Reactor that yielded thermal neutron fluences of approximately 2.0 x 10(12) or approximately 3.0 x 10(12) n/cm2, respectively, in the tumors. Untreated rats had a median postinitiation survival time of 21 days. Reactor radiation alone increased median postinitiation survival time to 26 (5.0 MW.min) or 28 (7.5 MW.min) days. The 12 rats that received 5 MW.min of BNCT had a median postinitiation survival time of 60 days. Two of these animals survived greater than 15 months. In the 7.5 MW.min group, the median survival time is not calculable since 6 of the 10 animals remain alive greater than 10 months after BNCT. The estimated radiation doses to tumors in the two BNCT groups were 14.2 and 25.6 Gy equivalents, respectively. Similar gliosarcoma-bearing rats treated with 15.0 or 22.5 Gy of 250-kilovolt peak x-rays had median survival times of only 26 or 31 days, respectively, after tumor initiation

Status of fusion technology development in JAERI stressing steady-state operation for future reactors

International Nuclear Information System (INIS)

Matsuda, Shinzaburo

2000-01-01

This paper reports on the progress of the fusion reactor technologies developed at the Japan Atomic Energy Research Institute (JAERI) and expected to lead to a future steady state operation reactor. In particular, superconducting coil technology for plasma confinement, NBI and RF systems technology for plasma control and current drive, fueling and pumping systems technology for particle control, heat removal technology, and development of long life materials are highlighted as the important key elements for the future steady state operation. It will be discussed how these key technologies have already been developed by the ITER (International Thermonuclear Experimental Reactor) technology R and D as well as by the Japanese domestic program, and which technologies are planned for the near future

Development of high intensity ion sources for a Tandem-Electrostatic-Quadrupole facility for Accelerator-Based Boron Neutron Capture Therapy.

Science.gov (United States)

Bergueiro, J; Igarzabal, M; Sandin, J C Suarez; Somacal, H R; Vento, V Thatar; Huck, H; Valda, A A; Repetto, M; Kreiner, A J

2011-12-01

Several ion sources have been developed and an ion source test stand has been mounted for the first stage of a Tandem-Electrostatic-Quadrupole facility For Accelerator-Based Boron Neutron Capture Therapy. A first source, designed, fabricated and tested is a dual chamber, filament driven and magnetically compressed volume plasma proton ion source. A 4 mA beam has been accelerated and transported into the suppressed Faraday cup. Extensive simulations of the sources have been performed using both 2D and 3D self-consistent codes. Copyright © 2011 Elsevier Ltd. All rights reserved.

Study on the dose distribution of the mixed field with thermal and epi-thermal neutrons for neutron capture therapy

International Nuclear Information System (INIS)

Kobayashi, Tooru; Sakurai, Yoshinori; Kanda, Keiji

1994-01-01

Simulation calculations using DOT 3.5 were carried out in order to confirm the characteristics of depth-dependent dose distribution in water phantom dependent on incident neutron energy. The epithermal neutrons mixed to thermal neutron field is effective improving the thermal neutron depth-dose distribution for neutron capture therapy. A feasibility study on the neutron energy spectrum shifter was performed using ANISN-JR for the KUR Heavy Water Facility. The design of the neutron spectrum shifter is feasible, without reducing the performance as a thermal neutron irradiation field. (author)

A Small-Animal Irradiation Facility for Neutron Capture Therapy Research at the RA-3 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Emiliano Pozzi; David W. Nigg; Marcelo Miller; Silvia I. Thorp; Amanda E. Schwint; Elisa M. Heber; Veronica A. Trivillin; Leandro Zarza; Guillermo Estryk

2007-11-01

The National Atomic Energy Commission of Argentina (CNEA) has constructed a thermal neutron source for use in Boron Neutron Capture Therapy (BNCT) applications at the RA-3 research reactor facility located in Buenos Aires. The Idaho National Laboratory (INL) and CNEA have jointly conducted some initial neutronic characterization measurements for one particular configuration of this source. The RA-3 reactor (Figure 1) is an open pool type reactor, with 20% enriched uranium plate-type fuel and light water coolant. A graphite thermal column is situated on one side of the reactor as shown. A tunnel penetrating the graphite structure enables the insertion of samples while the reactor is in normal operation. Samples up to 14 cm height and 15 cm width are accommodated.

Folate Functionalized Boron Nitride Nanotubes and their Selective Uptake by Glioblastoma Multiforme Cells: Implications for their Use as Boron Carriers in Clinical Boron Neutron Capture Therapy.

Science.gov (United States)

Ciofani, Gianni; Raffa, Vittoria; Menciassi, Arianna; Cuschieri, Alfred

2008-11-25

Boron neutron capture therapy (BNCT) is increasingly being used in the treatment of several aggressive cancers, including cerebral glioblastoma multiforme. The main requirement for this therapy is selective targeting of tumor cells by sufficient quantities of (10)B atoms required for their capture/irradiation with low-energy thermal neutrons. The low content of boron targeting species in glioblastoma multiforme accounts for the difficulty in selective targeting of this very malignant cerebral tumor by this radiation modality. In the present study, we have used for the first time boron nitride nanotubes as carriers of boron atoms to overcome this problem and enhance the selective targeting and ablative efficacy of BNCT for these tumors. Following their dispersion in aqueous solution by noncovalent coating with biocompatible poly-l-lysine solutions, boron nitride nanotubes were functionalized with a fluorescent probe (quantum dots) to enable their tracking and with folic acid as selective tumor targeting ligand. Initial in vitro studies have confirmed substantive and selective uptake of these nanovectors by glioblastoma multiforme cells, an observation which confirms their potential clinical application for BNCT therapy for these malignant cerebral tumors.

Folate Functionalized Boron Nitride Nanotubes and their Selective Uptake by Glioblastoma Multiforme Cells: Implications for their Use as Boron Carriers in Clinical Boron Neutron Capture Therapy

Directory of Open Access Journals (Sweden)

Ciofani Gianni

2008-01-01

Full Text Available Abstract Boron neutron capture therapy (BNCT is increasingly being used in the treatment of several aggressive cancers, including cerebral glioblastoma multiforme. The main requirement for this therapy is selective targeting of tumor cells by sufficient quantities of10B atoms required for their capture/irradiation with low-energy thermal neutrons. The low content of boron targeting species in glioblastoma multiforme accounts for the difficulty in selective targeting of this very malignant cerebral tumor by this radiation modality. In the present study, we have used for the first time boron nitride nanotubes as carriers of boron atoms to overcome this problem and enhance the selective targeting and ablative efficacy of BNCT for these tumors. Following their dispersion in aqueous solution by noncovalent coating with biocompatible poly-l-lysine solutions, boron nitride nanotubes were functionalized with a fluorescent probe (quantum dots to enable their tracking and with folic acid as selective tumor targeting ligand. Initial in vitro studies have confirmed substantive and selective uptake of these nanovectors by glioblastoma multiforme cells, an observation which confirms their potential clinical application for BNCT therapy for these malignant cerebral tumors.

A study on the utilization of hyper-thermal neutrons for neutron capture therapy

International Nuclear Information System (INIS)

Sakurai, Yoshinori; Kobayashi, Tooru; Kanda, Keiji

1993-01-01

The utilization of hyper-thermal neutrons, which have an energy spectrum of a Maxwellian distribution of a higher temperature than the room temperature of 300 K, was studied in order to improve the thermal neutron flux distribution at the deeper part in a living body for neutron capture therapy. Simulation calculations were carried out using MCNP-V3 in order to confirm the characteristics of hyper-thermal neutrons, i.e., (1) depth dependence of neutron energy spectrum, and (2) depth distribution of the reaction rate in a water phantom for materials with 1/v neutron absorption. It is confirmed that the hyper-thermal neutron irradiation can improve the thermal neutron flux distribution in the deeper and wider area in a living body compared with the thermal neutron irradiation. Practically, by the incidence of the hyper-thermal neutrons with a 3000 K Maxwellian distribution, the thermal neutron flux at 5 cm depth can be given about four times larger than by the incidence of the thermal neutrons of 300 K. (author)

Study of the interaction of boron-containing amino acids for the neutron capture therapy with biologically interesting compounds by using 'three-spot zone electrophoresis'

International Nuclear Information System (INIS)

Kitaoka, Yoshinori; Kobayashi, Mitsue; Morimoto, Tsuguhiro; Kirihata, Mitsunori; Ichimoto, Itsuo.

1995-01-01

As the boron carriers for boron neutron capture therapy, p-borono phenylalanine (BPA) is the boron compound which has been clinically used together with sodium borocaptate. It was found by the electrophoresis behavior that the BPA interacted with organic carboxylic acids in its dissolved state. In this paper, the electrophoresis behavior of general amino acids as seen in three-spot zone electrophoresis and the peculiar interaction of the amino acids having dihydroxyboryl radical are described. Zone electrophoresis has been developed as separation means, and three-spot process excludes the errors due to accidental factors as far as possible. The behaviors of zone electrophoresis of ordinary neutral amino acids, orthoboric acid and p-BPA are reported. For utilizing the features of boron neutron capture therapy, it is necessary to develop the carrier which is singularly taken into cancer cells. There is not a good method for discriminating normal cells and cancer cells. As for the administration of BPA to patients, its solubility is insufficient, therefore, its fructose complex has been used. The research on the biochemical peculiarity of boron is important. (K.I.)

Monte Carlo treatment planning and high-resolution alpha-track autoradiography for neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Zamenhof, R.G.; Lin, K.; Ziegelmiller, D.; Clement, S.; Lui, C.; Harling, O.K.

Monte Carlo simulations of thermal neutron flux distributions in a mathematical head model have been compared to experimental measurements in a corresponding anthropomorphic gelatin-based head phantom irradiated by a thermal neutron beam as presently available at the MITR-II Research Reactor. Excellent agreement between Monte Carlo and experimental measurements has encouraged us to employ the Monte Carlo simulation technique to approach treatment planning problems in neutron capture therapy. We have also implemented a high-resolution alpha-track autoradiography technique originally developed in our laboratory at MIT. Initial autoradiograms produced by this technique meet our expectations in terms of the high resolution available and the ability to etch tracks without concommitant destruction of stained tissue. Our preliminary results with computer-aided track distribution analysis indicate that this approach is very promising in being able to quantify boron distributions in tissue at the subcellular level with a minimum amount of operator effort necessary.

Establishment of optimal thermal neutron capture therapy for 5 types of human malignant melanoma

International Nuclear Information System (INIS)

Mishima, Yutaka

1993-03-01

A series of boron neutron capture therapy (BNCT) studies has already germinated in 1972, with a view to establishing the BNCT particularly suited for the treatment of various types of malignant melanoma, and has been succeeded by research teams comprised of multi-disciplinary members. Twelve patients (7 men and 5 women, aged from 50 to 85 years) with malignant melanoma have been treated with BNCT; among them, six patients were completely cured, four had extremely reduced tumors, and two were still in the clinical process. The present Progress Report is a compilation of 39 research presentations for the recent two years. In this report, three patients are described. Of these, one patient had deep-seated lesions in right and left lymph nodes. These lesions were cured by the use of D 2 O that allowed neutron beams to reach them. Application of positron emission tomography to the diagnosis of melanoma is a highlight in this Report. (N.K.)

Thermal-hydraulic analysis code development and application to passive safety reactor at JAERI

International Nuclear Information System (INIS)

Araya, F.

1995-01-01

After a brief overview of safety assessment process, the author describes the LOCA analysis code system developed in JAERI. It comprises audit calculation code (WREM, WREM-J2, Japanese own code and BE codes (2D/3D, ICAP, ROSA). The codes are applied to development of Japanese passive safety reactor concept JPSR. Special attention is paid to the passive heat removal system and phenomena considered to occur under loss of heat sink event. Examples of LOCA analysis based on operation of JPSR for the cases of heat removal by upper RHR and heat removal from core to atmosphere are given. Experiments for multi-dimensional flow field in RPV and steam condensation in water pool are used for understanding the phenomena in passive safety reactors. The report is in a poster form only. 1 tab., 13 figs

Selective uptake of p-boronophenylalanine by osteosarcoma cells for boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Ferrari, C. [Department of Surgery, Experimental Surgery Laboratory, University of Pavia, Piazza Botta, Pavia (Italy)], E-mail: ferraric@unipv.it; Zonta, C.; Cansolino, L.; Clerici, A.M.; Gaspari, A. [Department of Surgery, Experimental Surgery Laboratory, University of Pavia, Piazza Botta, Pavia (Italy); Altieri, S.; Bortolussi, S.; Stella, S. [Department of Nuclear and Theoretical Physics of University, Via Bassi, 6, Pavia (Italy); National Institute of Nuclear Physics (INFN) Section of Pavia, Via Bassi, 6, Pavia (Italy); Bruschi, P. [Department of Nuclear and Theoretical Physics of University, Via Bassi, 6, Pavia (Italy); Dionigi, P.; Zonta, A. [Department of Surgery, Experimental Surgery Laboratory, University of Pavia, Piazza Botta, Pavia (Italy)

2009-07-15

Osteosarcoma is the most common non-hematologic primary cancer type that develops in bone. Current osteosarcoma treatments combine multiagent chemotherapy with extensive surgical resection, which in some cases makes necessary the amputation of the entire limb. Nevertheless its infiltrative growth leads to a high incidence of local and distant recurrences that reduce the percentage of cured patients to less than 60%. These poor data required to set up a new therapeutic approach aimed to restrict the surgical removal meanwhile performing a radical treatment. Boron neutron capture therapy (BNCT), a particular radiotherapy based on the nuclear capture and fission reactions by atoms of {sup 10}B, when irradiated with thermal neutrons, could be a valid alternative or integrative option in case of osteosarcoma management, thanks to its peculiarity in selectively destroying neoplastic cells without damaging normal tissues. Aim of the present work is to investigate the feasibility of employing BNCT to treat the limb osteosarcoma. Boronophenylalanine (BPA) is used to carry {sup 10}B inside the neoplastic cells. As a first step the endocellular BPA uptake is tested in vitro on the UMR-106 osteosarcoma cell line. The results show an adequate accumulation capability. For the in vivo experiments, an animal tumor model is developed in Sprague-Dawley rats by means of an intrafemoral injection of UMR-106 cells at the condyle site. The absolute amounts of boron loading and the tumor to normal tissue {sup 10}B ratio are evaluated 2 h after the i.v. administration of BPA. The boron uptake by the neoplastic tissue is almost twice the normal one. However, higher values of boron concentration in tumor are requested before upholding BNCT as a valid therapeutic option in the treatment of osteosarcoma.

GPU-based prompt gamma ray imaging from boron neutron capture therapy

International Nuclear Information System (INIS)

Yoon, Do-Kun; Jung, Joo-Young; Suk Suh, Tae; Jo Hong, Key; Sil Lee, Keum

2015-01-01

Purpose: The purpose of this research is to perform the fast reconstruction of a prompt gamma ray image using a graphics processing unit (GPU) computation from boron neutron capture therapy (BNCT) simulations. Methods: To evaluate the accuracy of the reconstructed image, a phantom including four boron uptake regions (BURs) was used in the simulation. After the Monte Carlo simulation of the BNCT, the modified ordered subset expectation maximization reconstruction algorithm using the GPU computation was used to reconstruct the images with fewer projections. The computation times for image reconstruction were compared between the GPU and the central processing unit (CPU). Also, the accuracy of the reconstructed image was evaluated by a receiver operating characteristic (ROC) curve analysis. Results: The image reconstruction time using the GPU was 196 times faster than the conventional reconstruction time using the CPU. For the four BURs, the area under curve values from the ROC curve were 0.6726 (A-region), 0.6890 (B-region), 0.7384 (C-region), and 0.8009 (D-region). Conclusions: The tomographic image using the prompt gamma ray event from the BNCT simulation was acquired using the GPU computation in order to perform a fast reconstruction during treatment. The authors verified the feasibility of the prompt gamma ray image reconstruction using the GPU computation for BNCT simulations

On the compressor ring for the JAERI neutron science project

Energy Technology Data Exchange (ETDEWEB)

Yamane, Isao [National Lab. for High Energy Physics, Tsukuba, Ibaraki (Japan)

1997-11-01

(1), As long as a 1.5 GeV-8 MW linear accelerator is constructed in the JAERI neutron science center, it is quite reasonable to construct a 5 MW compressor ring as a driver of a high intensity spallation neutron source to generate pulsed neutron beams. (2), Suppression of beam loss around the compressor ring to an acceptable level is the most crucial subject to be coped with in designing a MW-class compressor ring. This subject should be successfully cleared by carefully studying and designing the overall system of accelerator and tunnel. (3), The `PSR instability` was comprehensively discussed in the NSNS workshop held at Santa Fe in March, 1997, as a remaining problem of a high intensity proton compressor ring. People of Los Alamos attributed it to an e-p instability. But some questions like the cause that makes some part of protons leak away from a beam bunch to a bunch gap are yet left open. (4), A new scheme of two step H{sup 0} injection is proposed to remove defects of the conventional one of Los Alamos PSR. (author)

A standardized method for beam design in neutron capture therapy

International Nuclear Information System (INIS)

Storr, G.J.: Harrington, B.V.

1993-01-01

A desirable end point for a given beam design for Neutron Capture Therapy (NCT) should be quantitative description of tumour control probability and normal tissue damage. Achieving this goal will ultimately rely on data from NCT human clinical trials. Traditional descriptions of beam designs have used a variety of assessment methods to quantify proposed or installed beam designs. These methods include measurement and calculation of open-quotes free fieldclose quotes parameters, such as neutron and gamma flux intensities and energy spectra, and figures-of-merit in tissue equivalent phantoms. The authors propose here a standardized method for beam design in NCT. This method would allow all proposed and existing NCT beam facilities to be compared equally. The traditional approach to determining a quantitative description of tumour control probability and normal tissue damage in NCT research may be described by the following path: Beam design → dosimetry → macroscopic effects → microscopic effects. Methods exist that allow neutron and gamma fluxes and energy dependence to be calculated and measured to good accuracy. By using this information and intermediate dosimetric quantities such as kerma factors for neutrons and gammas, macroscopic effect (absorbed dose) in geometries of tissue or tissue-equivalent materials can be calculated. After this stage, for NCT the data begins to become more sparse and in some areas ambiguous. Uncertainties in the Relative Biological Effectiveness (RBE) of some NCT dose components means that beam designs based on assumptions considered valid a few years ago may have to be reassessed. A standard method is therefore useful for comparing different NCT facilities

Are gadolinium contrast agents suitable for gadolinium neutron capture therapy?

Science.gov (United States)

De Stasio, Gelsomina; Rajesh, Deepika; Casalbore, Patrizia; Daniels, Matthew J; Erhardt, Robert J; Frazer, Bradley H; Wiese, Lisa M; Richter, Katherine L; Sonderegger, Brandon R; Gilbert, Benjamin; Schaub, Sebastien; Cannara, Rachel J; Crawford, John F; Gilles, Mary K; Tyliszczak, Tolek; Fowler, John F; Larocca, Luigi M; Howard, Steven P; Mercanti, Delio; Mehta, Minesh P; Pallini, Roberto

2005-06-01

Gadolinium neutron capture therapy (GdNCT) is a potential treatment for malignant tumors based on two steps: (1) injection of a tumor-specific (157)Gd compound; (2) tumor irradiation with thermal neutrons. The GdNC reaction can induce cell death provided that Gd is proximate to DNA. Here, we studied the nuclear uptake of Gd by glioblastoma (GBM) tumor cells after treatment with two Gd compounds commonly used for magnetic resonance imaging, to evaluate their potential as GdNCT agents. Using synchrotron X-ray spectromicroscopy, we analyzed the Gd distribution at the subcellular level in: (1) human cultured GBM cells exposed to Gd-DTPA or Gd-DOTA for 0-72 hours; (2) intracerebrally implanted C6 glioma tumors in rats injected with one or two doses of Gd-DOTA, and (3) tumor samples from GBM patients injected with Gd-DTPA. In cell cultures, Gd-DTPA and Gd-DOTA were found in 84% and 56% of the cell nuclei, respectively. In rat tumors, Gd penetrated the nuclei of 47% and 85% of the tumor cells, after single and double injection of Gd-DOTA, respectively. In contrast, in human GBM tumors 6.1% of the cell nuclei contained Gd-DTPA. Efficacy of Gd-DTPA and Gd-DOTA as GdNCT agents is predicted to be low, due to the insufficient number of tumor cell nuclei incorporating Gd. Although multiple administration schedules in vivo might induce Gd penetration into more tumor cell nuclei, a search for new Gd compounds with higher nuclear affinity is warranted before planning GdNCT in animal models or clinical trials.

Results from the Argonne, Los Alamos, JAERI collaboration

Energy Technology Data Exchange (ETDEWEB)

Meadows, J.; Smith, D.; Greenwood, L. [Argonne National Lab., IL (United States); Haight, R. [Los Alamos National Lab., NM (United States); Ikeda, Y.; Konno, C. [Japan Atomic Energy Research Inst., Ibaraki (Japan)

1993-07-01

Four sample packets containing elemental Ti, Fe, Ni, Cu, Nb, Ag, Eu, Tb and Hf have been irradiated in three distinct accelerator neutron fields, at Argonne National Laboratory and Los Alamos National Laboratory, USA, and Japan Atomic Energy Research Institute, Tokai, Japan. The acquired experimental data include differential cross sections and integral cross sections for the continuum neutron spectrum produced by 7-MeV deuterons incident on thick Be-metal target. The U-238(n,f) cross section was also measured at 10.3 MeV as a consistency check on the experimental technique. This the third progress report on a project which has been carried out under the auspices of an IAEA Coordinated Research Program entitled ``Activation Cross Sections for the Generation Of Long-lived Radionuclides of Importance in Fusion Reactor Technology``. The present report provides the latest results from this work. Comparison is made between the 14.7-MeV cross-section values obtained from the separate investigations at Argonne and JAERI. Generally, good agreement observed within the experimental errors when consistent sample parameters, radioactivity decay data and reference cross values are employed. A comparison is also made between the experimental results and those derived from calculations using a nuclear model. Experimental neutron information on the Be(d,n) neutron spectrum was incorporated in the comparisons for the integral results. The agreement is satisfactory considering the various uncertainties that are involved.

System of the advanced volume reduction facilities for LLW at JAERI

International Nuclear Information System (INIS)

Higuchi, Hidekazu; Monma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Henmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

2005-01-01

The Japan Atomic Energy Research Institute (JAERI) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the amount of the wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since June 1999. Radioactive wastes treated so far amount to 600 m 3 and the volume reduction ratio is from 1/2 to 1/3. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005. (author)

In-phantom dosimetry using the 13C(d,n)14N reaction for BNCT (boron neutron capture therapy)

International Nuclear Information System (INIS)

Burlon, Alejandro; Kreiner, Andres J.; White, S.; Blackburn, B.; Gierga, David; Yanch, Jacquelyn C.

2000-01-01

The use of the 13 C(d,n) 14 N reaction at E d =1.5 MeV for accelerator-based boron neutron capture therapy is investigated. The 13 C(d,n) 14 N reaction presents the advantages of carbon as a target material and its large cross section. The deuteron beam was produced by a tandem accelerator at MIT's Laboratory for Accelerator Beam Applications. The resulting neutron spectra were evaluated in terms of RBE-dose rates at different depths inside a water-filled brain phantom using a heavy water moderator and lead reflector assembly. All results were simulated using the code MCNP. (author)

Hadron Therapy: Past, Present and Perspectives

International Nuclear Information System (INIS)

Jones, D.T.L

1999-01-01

Fast neutron therapy began as long ago as 1938 and subsequently proton, alpha particle, heavy ion, pion and neutron capture therapy have been used. To date it is estimated that in excess of 45000 people have undergone some form of hadron therapy. In the future it is expected that fast neutron therapy will be used for selected tumour types for which neutron are known to show improved cure rates. The future trends in charged particle therapy will be driven by increasing commercialization. The future of neutron capture therapy will depend on current clinical trials with epithermal neutron beams and the development of new tumour-seeking drugs

Investigation on the neutron beam characteristics for boron neutron capture therapy with 3D and 2D transport calculations

International Nuclear Information System (INIS)

Kodeli, I.; Diop, C.M.; Nimal, J.C.

1994-01-01

In the framework of future Boron Neutron Capture Therapy (BNCT) experiments, where cells and animals irradiations are planned at the research reactor of Strasbourg University, the feasibility to obtain a suitable epithermal neutron beam is investigated. The neutron fluence and spectra calculations in the reactor are performed using the 3D Monte Carlo code TRIPOLI-3 and the 2D SN code TWODANT. The preliminary analysis of Al 2 O 3 and Al-Al 2 O 3 filters configurations are carried out in an attempt to optimize the flux characteristics in the beam tube facility. 7 figs., 7 refs

The roles of the Q (q) wave in lead I and QRS frontal axis for diagnosing loss of left ventricular capture during cardiac resynchronization therapy.

Science.gov (United States)

Cao, Yuan-Yuan; Su, Yan-Gang; Bai, Jin; Wang, Wei; Wang, Jing-Feng; Qin, Sheng-Mei; Ge, Jun-Bo

2015-01-01

Loss of left ventricular (LV) capture may lead to deterioration of heart failure in patients with cardiac resynchronization therapy (CRT). Recognition of loss of LV capture in time is important in clinical practice. A total of 422 electrocardiograms were acquired and analyzed from 53 CRT patients at 8 different pacing settings (LV only, right ventricle [RV] only, biventricular [BV] pacing with LV preactivation of 60, 40, 20, and 0 milliseconds and RV preactivation of 20 and 40 milliseconds). A modified Ammann algorithm by adding a third step-presence of Q (q, or QS) wave-to the original 2-step Ammann algorithm and a QRS axis shift method were devised to identify the loss of LV capture. The accuracy of modified Ammann algorithm was significantly higher than that of Ammann algorithm (78.9% vs. 69.1%, P capture. The LV preactivation, or simultaneous BV activation and LV lead positioned in nonposterior or noninferior wall can increase the diagnostic power of the modified Ammann algorithm and QRS axis shift method. © 2014 Wiley Periodicals, Inc.

Boron-containing thioureas for neutron capture therapy. Borhaltige Thioharnstoffe fuer die Neutroneneinfangtherapie

Energy Technology Data Exchange (ETDEWEB)

Ketz, H.

1993-10-21

Melanin is produced in large amounts in malignant melanotic melanomas. Because thiourea compounds are covalently incorporated into melanin during its biosynthesis, the preparation of boronated thiourea-derivatives is of particular interest for the BNCT (Boron Neutron Capture Therapy). Accumulation of boron in tumors by means of boronated thiourea-derivatives may therefore provide levels of [sup 10]B which are useful for BNCT. In BNCT the tumor containing the boron compound is irradiated with epithermal neutrons to generate He- and Li-nuclei from the [sup 10]B which can then destroy the tumor cells. Because of the short ranges of these particles (approximately one cell diameter) the damage will be almost exclusively confined to the tumor leaving normal tissue unharmed. High accumulation of 2-mercapto-1-methylimidazole (methimazole) in melanotic melanomas has been described in the literature. Boronated derivatives of methimazole were therefore synthesized. Boron was in the form of a boronic acid, a nido-carbonate and a mercaptoundeca hydro-closo-dodecaborate (BSH). The synthesis of the boron cluster derivatives of methimazole (nido-carborate- and BSH-derivatives) with 9 resp. 12 boron atoms in the molecule were expected to achieve higher concentrations of boron in the tumor than in the case of the boronic acid compound with its single boron atom. (orig.)

PEMODELAN KOLIMATOR DI RADIAL BEAM PORT REAKTOR KARTINI UNTUK BORON NEUTRON CAPTURE THERAPY

Directory of Open Access Journals (Sweden)

Bemby Yulio Vallenry

2015-03-01

Full Text Available Salah satu metode terapi kanker adalah Boron Neutron Capture Therapy (BNCT. BNCT memanfaatkan tangkapan neutron oleh 10B yang terendapkan pada sel kanker. Keunggulan BNCT dibandingkan dengan terapi radiasi lainnya adalah tingkat selektivitas yang tinggi karena tingkatannya adalah sel. Pada penelitian ini dilakukan pemodelan kolimator di radial beamport reaktor Kartini sebagai dasar pemilihan material dan manufature kolimator sebagai sumber neutron untuk BNCT. Pemodelan ini dilakukan dengan simulasi menggunakan perangkat lunak Monte Carlo N-Particle versi 5 (MCNP 5. MCNP 5 adalah suatu paket program untuk memodelkan sekaligus menghitung masalah transpor partikel dengan mengikuti sejarah hidup neutron semenjak lahir, bertranspor pada bahan hingga akhirnya hilang karena mengalami reaksi penyerapan atau keluar dari sistem. Pemodelan ini menggunakan variasi material dan ukurannya agar menghasilkan nilai dari tiap parameter-parameter yang sesuai dengan rekomendasi I International Atomic Energy Agency (IAEA untuk BNCT, yaitu fluks neutron epitermal (Фepi > 9 n.cm-2.s-1, rasio antara laju dosis neutron cepat dan fluks neutron epitermal (Ḋf/Фepi 0,7. Berdasarkan hasil optimasi dari pemodelan ini, material dan ukuran penyusun kolimator yang didapatkan yaitu 0,75 cm Ni sebagai dinding kolimator, 22 cm Al sebagai moderator dan 4,5 cm Bi sebagai perisai gamma. Keluaran berkas radiasi yang dihasilkan dari pemodelan kolimator radial beamport yaitu Фepi = 5,25 x 106 n.cm-2s-1, Ḋf/Фepi =1,17 x 10-13 Gy.cm2.n-1, Ḋγ/Фepi = 1,70 x 10-12 Gy.cm2.n-1, Фth/Фepi = 1,51 dan J/Фepi = 0,731. Berdasarkan penelitian ini, hasil optimasi 5 parameter sebagai persyaratan kolimator untuk BNCT yang keluar dari radial beam port tidak sepenuhnya memenuhi kriteria yang direkomendasikan oleh IAEA sehingga perlu dilakukan penelitian lebih lanjut agar tercapainya persyaratan IAEA. Kata kunci: BNCT, radial beamport, MCNP 5, kolimator   One of the cancer therapy methods is

Basic and clinical study of boron neutron capture therapy for malignant brain tumor

International Nuclear Information System (INIS)

Nose, Tadao; Matsumura, Akira; Nakai, Kei; Nakagawa, Kunio; Yoshii, Yoshihiko; Shibata, Yasushi; Yamamoto, Tetsuya; Hayakawa, Yoshinori; Yamada, Takashi

1998-01-01

Rat malignant cells (9L glioma cell) were exposed to neutron radiation after culturing with boron compounds; BSH and STA-BX909, and cell growing ability after the exposure was determined by colony forming assay. The effects of in vivo radiation were examined by measuring neutron flux levels in rat brain and skin aiming to use neutron radiation in clinical study. STA-BX909 was found to show a dose-dependent cell toxicity, which was higher than that of BSH. The radiation induced G2/M block in 9L-glioma cells and their cell cycles recovered thereafter in low-dose radiated cells, but high-dose radiated cells became aneuploidy. Furthermore, boron neutron capture therapy (BNCT) was applied in two patients, 41-year old woman with glioma grade 3 recurred and 45-year old man with glioblastoma multiforme. The former died from systemic deterioration due to ileus, but BNCT was made only one time although conventional radiotherapy is carried out for a relatively long period. Therefore, BNCT was thought to be beneficial from an aspect of 'quality of life' and the effects to repress a recurrence of cancer also seemed larger than the conventional one. (M.N.)

Basic and clinical study of boron neutron capture therapy for malignant brain tumor

Energy Technology Data Exchange (ETDEWEB)

Nose, Tadao; Matsumura, Akira; Nakai, Kei; Nakagawa, Kunio; Yoshii, Yoshihiko [Tsukuba Univ., Ibaraki (Japan). Inst. of Clinical Medicine; Shibata, Yasushi; Yamamoto, Tetsuya; Hayakawa, Yoshinori; Yamada, Takashi

1998-01-01

Rat malignant cells (9L glioma cell) were exposed to neutron radiation after culturing with boron compounds; BSH and STA-BX909, and cell growing ability after the exposure was determined by colony forming assay. The effects of in vivo radiation were examined by measuring neutron flux levels in rat brain and skin aiming to use neutron radiation in clinical study. STA-BX909 was found to show a dose-dependent cell toxicity, which was higher than that of BSH. The radiation induced G2/M block in 9L-glioma cells and their cell cycles recovered thereafter in low-dose radiated cells, but high-dose radiated cells became aneuploidy. Furthermore, boron neutron capture therapy (BNCT) was applied in two patients, 41-year old woman with glioma grade 3 recurred and 45-year old man with glioblastoma multiforme. The former died from systemic deterioration due to ileus, but BNCT was made only one time although conventional radiotherapy is carried out for a relatively long period. Therefore, BNCT was thought to be beneficial from an aspect of `quality of life` and the effects to repress a recurrence of cancer also seemed larger than the conventional one. (M.N.)

Basic study for development of new tumor specific agents for neutron capture therapy

International Nuclear Information System (INIS)

Matsumura, Akira; Nakagawa, Kunio; Yoshii, Yoshihiko; Nose, Tadao

1994-01-01

New tissue specific agents for neutron capture therapy was studied. Monoclonal labeled gadolinium-DTPA (Gd-MoAb) and porphyrin (ATN-10)-Gd-DTPA (Gd-ATN10) were studied as possible agents by using 9-L experimental brain tumor model. The tissue concentration were analyzed with magnetic resonance imaging (MRI) and inductively coupled plasma (ICP) analyzer. Gd-MoAb showed persistent retention in the tumor on MRI, but tissue gadolinium concentration was not detectable in the tumor by ICP analyzer, while there was high accumulation of Gd-MoAb in the liver. Gd-ATN10 showed prolonged and high accumulation in the tumor up to 48 hours on MRI. Gadolinium concentration reached up to 9 ppm in the tumor by 0.02 mmol/kg administration, but it disappeared within 6 hours after administration. This dissociation between MRI and ICP analysis was due to separation of ATN-10 and Gd-DTPA. As conclusions, the porphyrin compounds are potential agents for delivering gadolinium or boron specific to the tumor tissue, thus further improvement such as more stable conjugation between porphyrinfic to the tumor tissue, thus further improvement such as more stable conjugation between porphyrin and Gd-DTPA is needed. (author)

Research of accelerator-based neutron source for boron neutron capture therapy

International Nuclear Information System (INIS)

Li Changkai; Ma Yingjie; Tang Xiaobin; Xie Qin; Geng Changran; Chen Da

2013-01-01

Background: 7 Li (p, n) reaction of high neutron yield and low threshold energy has become one of the most important neutron generating reactions for Accelerator-based Boron Neutron Capture Therapy (BNCT). Purpose Focuses on neutron yield and spectrum characteristics of this kind of neutron generating reaction which serves as an accelerator-based neutron source and moderates the high energy neutron beams to meet BNCT requirements. Methods: The yield and energy spectrum of neutrons generated by accelerator-based 7 Li(p, n) reaction with incident proton energy from 1.9 MeV to 3.0 MeV are researched using the Monte Carlo code-MCNPX2.5.0. And the energy and angular distribution of differential neutron yield by 2.5-MeV incident proton are also given in this part. In the following part, the character of epithermal neutron beam generated by 2.5-MeV incident protons is moderated by a new-designed moderator. Results: Energy spectra of neutrons generated by accelerator-based 7 Li(p, n) reaction with incident proton energy from 1.9 MeV to 3.0 MeV are got through the simulation and calculation. The best moderator thickness is got through comparison. Conclusions: Neutron beam produced by accelerator-based 7 Li(p, n) reaction, with the bombarding beam of 10 mA and the energy of 2.5 MeV, can meet the requirement of BNCT well after being moderated. (authors)

An accelerator-based epithermal photoneutron source for boron neutron capture therapy

International Nuclear Information System (INIS)

Mitchell, H.E.

1996-04-01

Boron neutron capture therapy is an experimental binary cancer radiotherapy modality in which a boronated pharmaceutical that preferentially accumulates in malignant tissue is first administered, followed by exposing the tissue in the treatment volume to a thermal neutron field. Current usable beams are reactor-based but a viable alternative is the production of an epithermal neutron beam from an accelerator. Current literature cites various proposed accelerator-based designs, most of which are based on proton beams with beryllium or lithium targets. This dissertation examines the efficacy of a novel approach to BNCT treatments that incorporates an electron linear accelerator in the production of a photoneutron source. This source may help to resolve some of the present concerns associated with accelerator sources, including that of target cooling. The photoneutron production process is discussed as a possible alternate source of neutrons for eventual BNCT treatments for cancer. A conceptual design to produce epithermal photoneutrons by high photons (due to bremsstrahlung) impinging on deuterium targets is presented along with computational and experimental neutron production data. A clinically acceptable filtered epithermal neutron flux on the order of 10 7 neutrons per second per milliampere of electron current is shown to be obtainable. Additionally, the neutron beam is modified and characterized for BNCT applications by employing two unique moderating materials (an Al/AlF 3 composite and a stacked Al/Teflon design) at various incident electron energies

An accelerator-based epithermal photoneutron source for boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Mitchell, Hannah E. [Georgia Inst. of Technology, Atlanta, GA (United States)

1996-04-01

Boron neutron capture therapy is an experimental binary cancer radiotherapy modality in which a boronated pharmaceutical that preferentially accumulates in malignant tissue is first administered, followed by exposing the tissue in the treatment volume to a thermal neutron field. Current usable beams are reactor-based but a viable alternative is the production of an epithermal neutron beam from an accelerator. Current literature cites various proposed accelerator-based designs, most of which are based on proton beams with beryllium or lithium targets. This dissertation examines the efficacy of a novel approach to BNCT treatments that incorporates an electron linear accelerator in the production of a photoneutron source. This source may help to resolve some of the present concerns associated with accelerator sources, including that of target cooling. The photoneutron production process is discussed as a possible alternate source of neutrons for eventual BNCT treatments for cancer. A conceptual design to produce epithermal photoneutrons by high photons (due to bremsstrahlung) impinging on deuterium targets is presented along with computational and experimental neutron production data. A clinically acceptable filtered epithermal neutron flux on the order of 10⁷ neutrons per second per milliampere of electron current is shown to be obtainable. Additionally, the neutron beam is modified and characterized for BNCT applications by employing two unique moderating materials (an Al/AlF₃ composite and a stacked Al/Teflon design) at various incident electron energies.

Accelerator based-boron neutron capture therapy (BNCT)-clinical QA and QC

International Nuclear Information System (INIS)

Suzuki, Minoru; Tanaka, Hiroki; Sakurai, Yoshinori; Yong, Liu; Kashino, Genro; Kinashi, Yuko; Masunaga, Shinichiro; Ono, Koji; Maruhashi, Akira

2009-01-01

Alpha-particle and recoil Li atom yielded by the reaction ( 10 B, n), due to their high LET properties, efficiently and specifically kill the cancer cell that has incorporated the boron. Efficacy of this boron neutron capture therapy (BNCT) has been demonstrated mainly in the treatment of recurrent head/neck and malignant brain cancers in Kyoto University Research Reactor Institute (KUR). As the clinical trial of BNCT is to start from 2009 based on an accelerator (not on the Reactor), this paper describes the tentative outline of the standard operation procedure of BNCT for its quality assurance (QA) and quality control (QC) along the flow of its clinical practice. Personnel concerned in the practice involve the attending physician, multiple physicians in charge of BNCT, medical physicists, nurses and reactor stuff. The flow order of the actual BNCT is as follows: Pre-therapeutic evaluation mainly including informed consent and confirmation of the prescription; Therapeutic planning including setting of therapy volume, and of irradiation axes followed by meeting for stuffs' agreement, decision of irradiating field in the irradiation room leading to final decision of the axis, CT for the planning, decision of the final therapeutic plan according to Japan Atomic Energy Agency-Computational Dosimetry System (JCDS) and meeting of all related personnel for the final confirmation of therapeutic plan; and BNCT including the transport of patient to KUR, dripping of boronophenylalanine, setting up of the patient on the machine, blood sampling for pharmacokinetics, boron level measurement for decision of irradiating time, switch on/off of the accelerator, confirmation of patient's movement in the irradiated field after the neutron irradiation, blood sampling for confirmation of the boron level, and patient's leave from the room. The QA/QC check is principally to be conducted with the two-person rule. The purpose of the clinical trial is to establish the usefulness of BNCT

Experimental and Simulated Characterization of a Beam Shaping Assembly for Accelerator- Based Boron Neutron Capture Therapy (AB-BNCT)

International Nuclear Information System (INIS)

Burlon, Alejandro A.; Valda, Alejandro A.; Girola, Santiago; Minsky, Daniel M.; Kreiner, Andres J.

2010-01-01

In the frame of the construction of a Tandem Electrostatic Quadrupole Accelerator facility devoted to the Accelerator-Based Boron Neutron Capture Therapy, a Beam Shaping Assembly has been characterized by means of Monte-Carlo simulations and measurements. The neutrons were generated via the 7 Li(p, n) 7 Be reaction by irradiating a thick LiF target with a 2.3 MeV proton beam delivered by the TANDAR accelerator at CNEA. The emerging neutron flux was measured by means of activation foils while the beam quality and directionality was evaluated by means of Monte Carlo simulations. The parameters show compliance with those suggested by IAEA. Finally, an improvement adding a beam collimator has been evaluated.

IMPROVED COMPUTATIONAL CHARACTERIZATION OF THE THERMAL NEUTRON SOURCE FOR NEUTRON CAPTURE THERAPY RESEARCH AT THE UNIVERSITY OF MISSOURI

Energy Technology Data Exchange (ETDEWEB)

Stuart R. Slattery; David W. Nigg; John D. Brockman; M. Frederick Hawthorne

2010-05-01

Parameter studies, design calculations and initial neutronic performance measurements have been completed for a new thermal neutron beamline to be used for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The computational models used for the final beam design and performance evaluation are based on coupled discrete-ordinates and Monte Carlo techniques that permit detailed modeling of the neutron transmission properties of the filtering crystals with very few approximations. This is essential for detailed dosimetric studies required for the anticipated research program.

Boron Neutron Capture Therapy activity of diffused tumors at TRIGA Mark II in Pavia

Energy Technology Data Exchange (ETDEWEB)

Bortolussi, S.; Stella, S.; De Bari, A.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy)]|[National Institute of Nuclear Physics (INFN), Pavia (Italy); Bruschi, P.; Bakeine, J.G. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Clerici, A.; Ferrari, C.; Zonta, C.; Zonta, A. [Department of Surgery, University of Pavia, Pavia (Italy); Nano, R. [Department of Animal Biology, University of Pavia, Pavia (Italy)

2008-10-29

The Boron neutron Capture Therapy research in Pavia has a long tradition: it begun more than 20 years ago at the TRIGA Mark II reactor of the University. A technique for the treatment of the hepatic metastases was developed, consisting in explanting the liver treated with {sup 10}B, irradiating it in the thermal column of the reactor, and re-implanting the organ in the patient. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research will be presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,{alpha}) spectroscopy and neutron autoradiography. (authors)

Boron Neutron Capture Therapy activity of diffused tumors at TRIGA Mark II in Pavia

International Nuclear Information System (INIS)

Bortolussi, S.; Stella, S.; De Bari, A.; Altieri, S.; Bruschi, P.; Bakeine, J.G.; Clerici, A.; Ferrari, C.; Zonta, C.; Zonta, A.; Nano, R.

2008-01-01

The Boron neutron Capture Therapy research in Pavia has a long tradition: it begun more than 20 years ago at the TRIGA Mark II reactor of the University. A technique for the treatment of the hepatic metastases was developed, consisting in explanting the liver treated with 10 B, irradiating it in the thermal column of the reactor, and re-implanting the organ in the patient. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research will be presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,α) spectroscopy and neutron autoradiography. (authors)

Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE

International Nuclear Information System (INIS)

Hayashi, Takumi; Konishi, Satoshi; Nakamura, Hirofumi

1993-03-01

A first complete integrated test of the J-FCU (JAERI Fuel Cleanup System) and the ISS (Isotope Separation System) with full four cryogenic distillation columns was performed successfully with 100 grams of tritium. This test was performed as a part of a 25 day TSTA extended loop run on April - May 1992. Through this operation, the J-FCU operated stably and safely. No significant problems was caused on the interaction between the J-FCU and the ISS. J-FCU processed more than 5 N1/min of simulated fusion-fuel exhaust with wide range of impurities and transferred pure hydrogen isotopes to the ISS and exhausted tritium free impurities to the TWT (Tritium Waste Treatment System) continuously. This report describes the detail result of the J-FCU part test under a 25 day TSTA extended loop run and discuss the JFCU performance. (author)

Present state of tandem superconductive booster of JAERI

Energy Technology Data Exchange (ETDEWEB)

Takeuchi, Suehiro; Matsuda, Makoto; Kanazawa, Shuhei; Yoshida, Tadashi; Ouchi, Isao; Shoji, Tokio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-12-01

The superconductive booster constructed rear-stage accelerator of the tandem accelerator of the Tokai Research Establishment, JAERI (Japan Atomic Energy Research Institute), was completed in construction of its whole system on October, 1993, and through its beam accelerating test and remodulation its design characteristics were established on September, 1994. From November, 1994 to April, 1995 a repulsion-forming nuclear isolation apparatus was installed to modulate at target room, and was begun to use on June, 1995. The beam reaccelerated at the booster was used mainly for nuclear spectroscopy experiment, a collaborative research was developed using mini-crystal balls made by collecting from University of Tsukuba and so forth. The accelerating part of the booster is a phase independent setting type Linac consisting of 40 niobium superconducting holes with 1/4 wave-length type and 130 MHz in frequency, in which a hole can form 5 MV/m of accelerating electric field for 4 W of radio frequency spent power of 0.75 MV of accelerating voltage per hole, to form 30 MV of voltage in a whole. 4 holes are contained into each 10 cryostats, respectively. In accelerating tests, Si, Cl, Ni, Ge, Ag, I and Au ions are accelerated to establish 30 mV of total accelerating voltage in its design value, which reaches to their expected energy characteristics. Its used days in this year are 25 days after beginning of its use, and operating days of the cooling apparatus was 135 days in total. (G.K.)

Cell cycle dependence of boron uptake in various boron compounds used for neutron capture therapy

International Nuclear Information System (INIS)

Yoshida, F.; Matsumura, A.; Shibata, Y.; Yamamoto, T.; Nose, T.; Okumura, M.

2000-01-01

In neutron capture therapy, it is important that the tumor take boron in selectively. Furthermore, it is ideal when the uptake is equal in each tumor cell. Some indirect proof of differences in boron uptake among neoplastic cell cycles has been documented. However, no investigation has yet measured boron uptake directly. Using flow cytometry, in the present study cells were sorted by G0/G1 phase and G2/M phase, and the boron concentration of each fraction was measured with inductively coupled plasma-atomic emission spectroscopy (ICP-AES). The results were that BSH (sodiumborocaptate) and BPA (p-boronophenylalanine) had higher rates of boron uptake in the G2/M group than in the G0/G1 group. However, in BPA the difference was more prominent, which revealed a 2.2-3.3 times higher uptake of boron in the G2/M group than in the G0/G1 group. (author)

Boron microquantification in oral mucosa and skin following administration of a neutron capture therapy agent

International Nuclear Information System (INIS)

Kiger, S.W. III; Micca, P.L.; Morris, G.M.; Coderre, J.A.

2002-01-01

Clinical trials of boron neutron capture therapy (BNCT) for intracranial tumours using boronphenylalanine-fructose undertaken at Harvard-MIT and Brookhaven National Laboratory have observed acute normal tissue reactions in the skin and oral mucosa. Because the range of the 10 B(n,a) 7 Li reaction products is very short, 10-14 μm combined, knowledge of the 10B microdistribution in tissue is critical for understanding the microdosimetry and radiobiology of BNCT. This paper reports measurements of the microdistribution of 10 B in an animal model, rat skin and tongue, using high resolution quantitative autoradiography (HRQAR), a neutron-induced track etch autoradiographic technique. The steep spatial gradient and high absolute value relative to blood of the 10 B concentration observed in some strata of the rat tongue epithelium and skin are important for properly evaluating the radiobiology and the biological effectiveness factors for normal tissue reactions such as oral mucositis, which are generally assessed using the blood boron concentration rather than the tissue boron concentration. (author)

Stress analysis of blanket vessel for JAERI experimental fusion reactor

International Nuclear Information System (INIS)

Sako, K.; Minato, A.

1979-01-01

A blanket structure of JAERI Experimental Fusion Reactor (JXFR) consists of about 2,300 blanket cells with round cornered rectangular cross sections (twelve slightly different shapes) and is placed in a vacuum vessel. Each blanket vessel is a double-walled thin-shell structure made of Type 316 stainless steel with a spherical domed surface at the plasma side. Ribs for coolant channel are provided between inner and outer walls. The blanket cell contains Li 2 O pebbles and blocks for tritium breeding and stainless steel blocks for neutron reflection. A coolant is helium gas at 10 kgf/cm 2 (0.98 MPa) and its inlet and outlet temperatures are 300 0 C and 500 0 C. The maxima of heat flux and nuclear heating rate at the first wall are 12 W/cm 2 and 2 W/cc. A design philosophy of the blanket structure is based on high tritium breeding ratio and more effective shielding performance. The thin-shell vessel with a rectangular cross section satisfies the design philosophy. We have designed the blanket structure so that the adjacent vessels are mutually supporting in order to decrease the large deformation and stress due to internal pressure in case of the thin-shell vessel. (orig.)

Radiation Transport Simulation for Boron Neutron Capture Therapy (BNCT)

Energy Technology Data Exchange (ETDEWEB)

Ziegner, M.; Blaickner, M. [AIT Austrian Institute of Technology GmbH, Health and Environment Department, Molecular Medicine, Muthgasse 11, 1190 Wien (Austria); Ziegner, M.; Khan, R.; Boeck, H. [Vienna University of Technology, Institute of Atomic and Subatomic Physics, Stadionallee 2, 1020 Wien (Austria); Bortolussi, S.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, National Institute of Nuclear Physics (INFN) Pavia Section, Pavia (Italy); Schmitz, T.; Hampel, G. [Nuclear Chemistry, University of Mainz, Fritz Strassmann Weg 2, 55099 Mainz (Germany)

2011-07-01

This work is part of a larger project initiated by the University of Mainz and aiming to use the university's TRIGA reactor to develop a treatment for liver metastases based on Boron Neutron Capture Therapy (BNCT). Diffuse distribution of cancerous cells within the organ makes complete resection difficult and the vicinity to radiosensitive organs impedes external irradiation. Therefore the method of 'autotransplantation', first established at the University of Pavia, is used. The liver is taken out of the body, irradiated in the thermal column of the reactor, therewith purged of metastases and then reimplanted. A highly precise dosimetry system is to be developed by means of measurements at the University of Mainz and computational calculations at the AIT. The stochastic MCNP-5 Monte Carlo-Code, developed by Los Alamos Laboratories, is applied. To verify the calculations of the flux and the absorbed dose in matter a number of measurements are performed irradiating different phantoms and liver sections in a 20cm x 20cm beam tube, which was created by removing graphite blocks from the thermal column of the reactor. The detector material consists of L- {alpha} -alanine pellets which are thought to be the most suitable because of their good tissue equivalence, small size and their wide response range. Another experiment focuses on the determination of the relative biological effectiveness (RBE-factor) of the neutron and photon dose for liver cells. Therefore cell culture plates with the cell medium enriched with {sup 157}Gd and {sup 10}B at different concentrations are irradiated. With regard to the alanine pellets MCNP-5 calculations give stable results. Nevertheless the absorbed dose is underestimated compared to the measurements, a phenomenon already observed in previous works. The cell culture calculations showed the enormous impact of the added isotopes with high thermal neutron cross sections, especially {sup 157}Gd, on the absorbed dose

OPTIMIZATION OF THE EPITHERMAL NEUTRON BEAM FOR BORON NEUTRON CAPTURE THERAPY AT THE BROOKHAVEN MEDICAL RESEARCH REACTOR.

Energy Technology Data Exchange (ETDEWEB)

HU,J.P.; RORER,D.C.; RECINIELLO,R.N.; HOLDEN,N.E.

2002-08-18

Clinical trials of Boron Neutron Capture Therapy for patients with malignant brain tumor had been carried out for half a decade, using an epithermal neutron beam at the Brookhaven's Medical Reactor. The decision to permanently close this reactor in 2000 cut short the efforts to implement a new conceptual design to optimize this beam in preparation for use with possible new protocols. Details of the conceptual design to produce a higher intensity, more forward-directed neutron beam with less contamination from gamma rays, fast and thermal neutrons are presented here for their potential applicability to other reactor facilities. Monte Carlo calculations were used to predict the flux and absorbed dose produced by the proposed design. The results were benchmarked by the dose rate and flux measurements taken at the facility then in use.

Boron neutron capture therapy for clear cell sarcoma (CCS): Biodistribution study of p-borono-L-phenylalanine in CCS-bearing animal models

International Nuclear Information System (INIS)

Andoh, T.; Fujimoto, T.; Sudo, T.; Fujita, I.; Imabori, M.; Moritake, H.; Sugimoto, T.; Sakuma, Y.; Takeuchi, T.; Kawabata, S.; Kirihata, M.; Akisue, T.; Yayama, K.; Kurosaka, M.; Miyatake, S.; Fukumori, Y.; Ichikawa, H.

2011-01-01

Clear cell sarcoma (CCS) is a rare melanocytic malignant tumor with a poor prognosis. Our previous study demonstrated that in vitro cultured CCS cells have the ability to highly uptake L-BPA and thus boron neutron capture therapy could be a new option for CCS treatment. This paper proved that a remarkably high accumulation of 10 B (45–74 ppm) in tumor was obtained even in a CCS-bearing animal with a well-controlled biodistribution followed by intravenous administration of L-BPA-fructose complex (500 mg BPA/kg).

Boron neutron capture therapy for clear cell sarcoma (CCS): Biodistribution study of p-borono-L-phenylalanine in CCS-bearing animal models

Energy Technology Data Exchange (ETDEWEB)

Andoh, T. [Laboratory of Pharmaceutical Technology, Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan); Fujimoto, T. [Department of Orthopaedic Surgery, Hyogo Cancer Center, Akashi 673-0021 (Japan); Sudo, T. [Section of Translational Research, Hyogo Cancer Center, Akashi 673-0021 (Japan); Fujita, I.; Imabori, M. [Department of Orthopaedic Surgery, Hyogo Cancer Center, Akashi 673-0021 (Japan); Moritake, H. [Department of Pediatrics, Miyazaki University, Kiyotake 889-1692 (Japan); Sugimoto, T. [Department of Pediatrics, Saiseikai Shigaken Hospital, Ritto 520-3046 (Japan); Sakuma, Y. [Department of Pathology, Hyogo Cancer Center, Akashi 673-0021 (Japan); Takeuchi, T. [Department of Pathology, Kochi University, Nangoku 783-8505 (Japan); Kawabata, S. [Department of Neurosurgery, Osaka Medical College, Osaka 569-8686 (Japan); Kirihata, M. [Graduate School of Life and Environmental Sciences, Osaka Prefecture University, Sakai 599-8531 (Japan); Akisue, T. [Department of Orthopaedic Surgery, Kobe University Graduate School of Medicine, Kobe 650-0017 (Japan); Yayama, K. [Laboratory of Cardiovascular Pharmacology, Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan); Kurosaka, M. [Department of Orthopaedic Surgery, Kobe University Graduate School of Medicine, Kobe 650-0017 (Japan); Miyatake, S. [Department of Neurosurgery, Osaka Medical College, Osaka 569-8686 (Japan); Fukumori, Y. [Laboratory of Pharmaceutical Technology, Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan); Ichikawa, H., E-mail: ichikawa@pharm.kobegakuin.ac.jp [Laboratory of Pharmaceutical Technology, Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan)

2011-12-15

Clear cell sarcoma (CCS) is a rare melanocytic malignant tumor with a poor prognosis. Our previous study demonstrated that in vitro cultured CCS cells have the ability to highly uptake L-BPA and thus boron neutron capture therapy could be a new option for CCS treatment. This paper proved that a remarkably high accumulation of {sup 10}B (45-74 ppm) in tumor was obtained even in a CCS-bearing animal with a well-controlled biodistribution followed by intravenous administration of L-BPA-fructose complex (500 mg BPA/kg).

Effectiveness of boron neutron capture therapy for recurrent head and neck malignancies

Energy Technology Data Exchange (ETDEWEB)

Kato, Itsuro [Department of Oral and Maxillofacial Surgery, II Osaka University, Graduate School of Dentistry, Osaka (Japan)], E-mail: katoitsu@dent.osaka-u.ac.jp; Fujita, Yusei [Department of Oral and Maxillofacial Surgery, II Osaka University, Graduate School of Dentistry, Osaka (Japan); Maruhashi, Akira [Radiation Oncology Research Laboratory, Research Reactor Institut, Kyoto University, Osaka (Japan); Kumada, Hiroaki [Japan Atomic Energy Agency, Tokai Research and Development Center, Ibaraki (Japan); Ohmae, Masatoshi [Department of Oral and Maxillofacial Surgery, Izimisano Municipal Hospital, Rinku General Hospital, Izumisano, Osaka (Japan); Kirihata, Mitsunori [Graduate School of Environment and Life Science, Osaka prefectural University, Osaka (Japan); Imahori, Yoshio [Department of Neurosurgery, Kyoto Prefectural University, Kyoto (Japan); CEO of Cancer Intelligence Care Systems, Inc., Tokyo (Japan); Suzuki, Minoru [Radiation Oncology Research Laboratory, Research Reactor Institut, Kyoto University, Osaka (Japan); Sakrai, Yoshinori [Graduate School of Medicine, Sapporo Medical University of Medicine, Hokkaido (Japan); Sumi, Tetsuro; Iwai, Soichi; Nakazawa, Mitsuhiro [Department of Oral and Maxillofacial Surgery, II Osaka University, Graduate School of Dentistry, Osaka (Japan); Murata, Isao; Miyamaru, Hiroyuki [Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University (Japan); Ono, Koji [Radiation Oncology Research Laboratory, Research Reactor Institut, Kyoto University, Osaka (Japan)

2009-07-15

It is necessary to explore new treatments for recurrent head and neck malignancies (HNM) to avoid severe impairment of oro-facial structures and functions. Boron neutron capture therapy (BNCT) is tumor-cell targeted radiotherapy that has significant superiority over conventional radiotherapies in principle. We have treated with BNCT 42 times for 26 patients (19 squamous cell carcinomas (SCC), 4 salivary gland carcinomas and 3 sarcomas) with a recurrent and far advanced HNM since 2001. Results of (1) {sup 10}B concentration of tumor/normal tissue ratios (T/N ratio) of FBPA-PET studies were SCC: 1.8-5.7, sarcoma: 2.5-4.0, parotid tumor: 2.5-3.7. (2) Therapeutic effects were CR: 12 cases, PR: 10 cases, PD: 3 cases NE (not evaluated): 1 case. Response rate was 85%. (3) Improvement of QOL such as a relief of severe pain, bleeding, and exudates at the local lesion, improvement of PS, disappearance of ulceration, covered with normal skin and preserved oral and maxillofacial functions and tissues. (4) Survival periods after BNCT were 1-72 months (mean: 13.6 months). Six-year survival rate was 24% by Kaplan-Meier analysis. (5) Adverse-events were transient mucositis and alopecia in most of the cases; three osteomyelitis and one brain necrosis were recognized. These results indicate that BNCT represents a new and promising treatment approach for advanced HNM.

Towards gadolinium neutron capture therapy

International Nuclear Information System (INIS)

Stalpers, L.; Kuipers, S.; Vroegindeweij, C.; Stecher-Rasmussen, F.; Slotman, B.

2000-01-01

As glioblastoma multiforme has macroscopic areas with poor vascularisation, and thereby poor uptake of an NCT-agent, the long-range γ-rays from GdNCT might enhance dose deposition compared to BNCT and to conformal photon therapy. Multicellular spheroids from a human glioblastoma cell line (Gli-6) were irradiated with conventional X-rays, with neutrons only (from the NRG Argonaut Reactor, LFR), and with neutrons (from the LFR) + 157 Gd-DTPA (240 ppm 157 Gd). Preliminary results demonstrate that after neutron irradiation in the presence of 157 Gd, the spheroids showed growth arrest. By 3D treatment planning calculations on MRI's from patients with brain tumours, dose volume histograms (DVH) for GdNCT were compared to DVH for conventional conformal radiotherapy. The calculations indicate that GdNCT on patients with large, deep-seated tumours yields better tumour/brain dose distribution than conformal radiotherapy. (author)

Intracellular targeting of mercaptoundecahydrododecaborate (BSH) to malignant glioma by transferrin-PEG liposomes for boron neutron capture therapy (BNCT)

International Nuclear Information System (INIS)

Doi, Atsushi; Miyatake, Shin-ichi; Iida, Kyouko

2006-01-01

Malignant glioma is one of the most difficult tumor to control with usual therapies. In our institute, we select boron neutron capture therapy (BNCT) as an adjuvant radiation therapy after surgical resection. This therapy requires the selective delivery of high concentration of 10 B to malignant tumor tissue. In this study, we focused on a tumor-targeting 10 B delivery system (BDS) for BNCT that uses transferrin-conjugated polyethylene-glycol liposome encapsulating BSH (TF-PEG liposome-BSH) and compared 10 B uptake of the tumor among BSH, PEG liposome-BSH and TF-PEG liposome-BSH. In vitro, we analyzed 10 B concentration of the cultured human U87Δ glioma cells incubated in medium containing 20 μg 10 B/ml derived from each BDS by inductively coupled plasma atomic emission spectrometry (ICP-AES). In vivo, human U87Δ glioma-bearing nude mice were administered with each BDS (35mg 10 B/kg) intravenously. We analyzed 10 B concentration of tumor, normal brain and blood by ICP-AES. The TF-PEG liposome-BSH showed higher absolute concentration more than the other BDS. Moreover, TF-PEG liposome-BSH decreased 10 B concentration in blood and normal tissue while it maintained high 10 B concentration in tumor tissue for a couple of days. This showed the TF-PEG liposome-BSH caused the selective delivery of high concentration of 10 B to malignant tumor tissue. The TF-PEG liposome-BSH is more potent BDS for BNCT to obtain absolute high 10 B concentration and good contrast between tumor and normal tissue than BSH and PEG liposome-BSH. (author)

Design and R and D activities on ceramic breeder blanket for fusion experimental reactors in JAERI

International Nuclear Information System (INIS)

Kurasawa, T.; Takatsu, H.; Sato, S.; Nakahira, M.; Furuya, K.; Hashimoto, T.; Kawamura, H.; Kuroda, T.; Tsunematsu, T.; Seki, M.

1995-01-01

Design and R and D activities on ceramic breeder blanket of a fusion experimental reactor have been progressed in JAERI. A layered pebble bed type ceramic breeder blanket with water cooling is a prime candidate concept. Design activities have been concentrated on improvement of the design by conducting detailed analyses and also by fabrication procedure consideration based on the current technologies. A wide variety of R and Ds have also been conducted in accordance with the design activities. Development of fabrication technology of the blanket box structure and its mechanical testing, elementary testing on thermal performances of the pebble bed, and engineering-oriented material tests of breeder and beryllium pebbles are the main achievements during the last two years. (orig.)

Enhanced therapeutic effect on murine melanoma and angiosarcoma cells by boron neutron capture therapy using a boronated metalloporphyrin

International Nuclear Information System (INIS)

Yamada, Yoshihiko; Ichihashi, Masamitsu; Kahl, S.B.; Toda, Ken-ichi.

1994-01-01

We have already achieved successful treatment of several human patients with malignant melanoma by boron neutron capture therapy (BNCT) using 10 B 1 -paraboronophenylalanine ( 10 B 1 -BPA·HCl). In this study we used a new compound, a manganese boronated protoporphyrin (Mn- 10 BOPP), and compared it to 10 B 1 -BPA·HCl with respect to uptake in murine melanoma and angiosarcoma cells as well as to their cell killing effect. 10 B uptake was measured in a new method, and the new compound was much more incorporated into both cells than 10 B 1 -BPA·HCl. Furthermore, melanoma and angiosarcoma cells preincubated with the new compound were 15 to 20 times more efficiently killed by BNCT than cells preincubated with 10 B 1 -BPA·HCl. (author)

Test of the palladium diffuser in the JAERI Fuel Cleanup System in the Tritium Systems Test Assembly

International Nuclear Information System (INIS)

Konishi, Satoshi; Hayashi, Takumi; O-hira, Shigeru

1993-03-01

The JAERI Fuel Cleanup System (JFCU) is a major subsystem of the TSTA simulated fusion fuel loop. The palladium diffuser, that accepts simulated plasma exhaust and purifies the hydrogen isotopes mixture for the feed to the Isotope Separation System, was tested with deuterium to investigate the characteristics of the components. Permeation flow rate is a linear function of the difference of the square root of the pressure across the palladium alloy membrane. However at the low pressure region, an impediment on the permeation was observed. It was suspected to be caused by the impurity adsorbed on the surface of the permeated side of the membrane and was reduced by oxidation treatment. (author)

Present status of the negative ion sources and injectors at JAERI tandem accelerator facility

International Nuclear Information System (INIS)

Minehara, E.; Yoshida, T.; Abe, S.

1988-01-01

The JAERI tandem accelerator began regular operation with the 350 kV negative ion jnjector and 3 kinds of nagative ion sources (Direct Extraction Duoplasmatron Ion Source, Heinickie Penning Ion Source, Negative Ion Sputter Source (Refocus-UNIS)) since 1982. An extension with the injector was constructed in 1984, (1) to increase reliability of all devices in the injector, (2) to exclude completely any unsafe operation in the injector, and (3) to tune several ion sources simultaneously, while a certain ion source is in operation. After the extended injector became available, we have been able to run the whole injector system very safely, steadily and effectively, and have had few troubles. Currently, the second injector has been constructed in order to obtain a full strength of resistance against any sudden troubles in the injector. Several other operational and developmental items will be discussed in the text briefly. (author)

{sup 1}H and {sup 10}B NMR and MRI investigation of boron- and gadolinium-boron compounds in boron neutron capture therapy

Energy Technology Data Exchange (ETDEWEB)

Bonora, M., E-mail: marco.bonora@unipv.it [Physics Department ' A. Volta' , University of Pavia, Via Bassi 6, 27100 Pavia (Italy)] [CNISM Unit (Italy); Corti, M.; Borsa, F. [Physics Department ' A. Volta' , University of Pavia, Via Bassi 6, 27100 Pavia (Italy)] [CNISM Unit (Italy); Bortolussi, S.; Protti, N.; Santoro, D.; Stella, S.; Altieri, S. [Nuclear and Theoretical Physics Department, University of Pavia, Via Bassi 6, 27100 Pavia (Italy)] [INFN Pavia (Italy); Zonta, C.; Clerici, A.M.; Cansolino, L.; Ferrari, C.; Dionigi, P. [Surgical Sciences Department, Experimental Surgery Laboratory, University of Pavia, Pavia (Italy); Porta, A.; Zanoni, G.; Vidari, G. [Organic Chemistry Department, University of Pavia, Via Taramelli 10, 27100 Pavia (Italy)

2011-12-15

{sup 10}B molecular compounds suitable for Boron Neutron Capture Therapy (BNCT) are tagged with a Gd(III) paramagnetic ion. The newly synthesized molecule, Gd-BPA, is investigated as contrast agent in Magnetic Resonance Imaging (MRI) with the final aim of mapping the boron distribution in tissues. Preliminary Nuclear Magnetic Resonance (NMR) measurements, which include {sup 1}H and {sup 10}B relaxometry in animal tissues, proton relaxivity of the paramagnetic Gd-BPA molecule in water and its absorption in tumoral living cells, are reported.

Beam neutron energy optimization for boron neutron capture therapy using monte Carlo method

International Nuclear Information System (INIS)

Pazirandeh, A.; Shekarian, E.

2006-01-01

In last two decades the optimal neutron energy for the treatment of deep seated tumors in boron neutron capture therapy in view of neutron physics and chemical compounds of boron carrier has been under thorough study. Although neutron absorption cross section of boron is high (3836b), the treatment of deep seated tumors such as glioblastoma multiform requires beam of neutrons of higher energy that can penetrate deeply into the brain and thermalized in the proximity of the tumor. Dosage from recoil proton associated with fast neutrons however poses some constraints on maximum neutron energy that can be used in the treatment. For this reason neutrons in the epithermal energy range of 10eV-10keV are generally to be the most appropriate. The simulation carried out by Monte Carlo methods using MCBNCT and MCNP4C codes along with the cross section library in 290 groups extracted from ENDF/B6 main library. The ptimal neutron energy for deep seated tumors depends on the sue and depth of tumor. Our estimated optimized energy for the tumor of 5cm wide and 1-2cm thick stands at 5cm depth is in the range of 3-5keV

About neutron capture therapy method development at WWR-SM reactor in institute of Nuclear Physics of Uzbekistan Academy of Sciences

International Nuclear Information System (INIS)

Abdullaeva, G.A.; Baytelesov, S.A.; Dosimbaev, A.A.; Koblik, Yu.N.; Gritsay, O.O.

2006-01-01

Full text: Neutron capture therapy (NCT) is developing method of swellings treatment, on which specialists set one's serious hopes, as at its realization the practical possibilities of the effect on any swellings open. The essence of method is simple and lies in the fact that to the swelling enter preparation containing boron or gadolinium, which one have a large capture cross-section of the thermal and slow neutrons. Then the swelling is irradiated once with the slow (epithermal) neutron beam with fluency about 10 9 neutrons /sm 2 s for a short time and single. As a result of thermal neutrons capture by the boron (or gadolinium) nuclei secondary radiation which affecting swelling cells is emitted. NCT of oncologic diseases makes the specific demands to physical parameters of neutron beams. Now research reactors are often used for NCT. However, research reactor WWR-SM (INP, Uzbekistan AS, Tashkent) doesn't provide with the epithermal neutron beams and to develop this technique the reactor, first of all, needs for obtaining the epithermal neutron beams with energy spectrum in range from 1 eV up to 10 keV and with intensity ∼ 10 9 neutron /sm 2 s. Practically it is connected with upgrade of at least one of existed reactor channels, namely with equipping with the special equipment (filters), forming from the reactor spectrum the beam of necessary energy neutrons. It requires realization of preliminary model calculations, including calculations of capture cross-sections, of filters types and their geometrical parameters on the basis of optimal selected materials. Such calculations, as a rule, are carried out on the basis of Monte-Carlo method and designed software for calculation of nuclear reactor physical and technical characteristics [1]. In this work the calculation results of devices variants and problems discussion, related with possibility of WWR-SM reactor using for NCT are presented. (author)

Biodistribution of nanoparticles of hydrophobic gadopentetic-acid derivative prepared with a planetary ball mill for neutron-capture therapy of cancer

International Nuclear Information System (INIS)

Nabeta, Chika; Ichikawa, Hideki; Fukumori, Yoshinobu

2006-01-01

Nanoparticles of hydrophobic gadopentetic-acid derivatives (Gd-nanoGR) were prepared with a wet ball-milling process for gadolinium neutron-capture therapy. Ball-milling of solid mass of gadopentetic acid distearylamide with soybean lecithin as a dispersant in the presence of water and subsequent sonication at 70degC resulted in the Gd-nanoGR with the particle size of 63 nm. Biodistribution study using melanoma-bearing hamsters demonstrated that the i.v. injection of the Gd-nanoGR made a higher gadolinium accumulation in tumor (109 μg Gd/g wet tumor at 6h after administration), when compared with the gadolinium-loaded micellar-like nanoparticles previously reported. (author)

Boron neutron capture therapy for clear cell sarcoma (CCS): biodistribution study of p-borono-L-phenylalanine in CCS-bearing animal models.

Science.gov (United States)

Andoh, T; Fujimoto, T; Sudo, T; Fujita, I; Imabori, M; Moritake, H; Sugimoto, T; Sakuma, Y; Takeuchi, T; Kawabata, S; Kirihata, M; Akisue, T; Yayama, K; Kurosaka, M; Miyatake, S; Fukumori, Y; Ichikawa, H

2011-12-01

Clear cell sarcoma (CCS) is a rare melanocytic malignant tumor with a poor prognosis. Our previous study demonstrated that in vitro cultured CCS cells have the ability to highly uptake l-BPA and thus boron neutron capture therapy could be a new option for CCS treatment. This paper proved that a remarkably high accumulation of (10)B (45-74 ppm) in tumor was obtained even in a CCS-bearing animal with a well-controlled biodistribution followed by intravenous administration of L-BPA-fructose complex (500 mg BPA/kg). Copyright © 2011 Elsevier Ltd. All rights reserved.