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Journal Articles

Development of alternative $$^3$$He NDA detector system

Koizumi, Mitsuo; Sakasai, Kaoru; Kureta, Masatoshi; Nakamura, Hironobu

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(11), p.642 - 646, 2016/11

no abstracts in English

Journal Articles

Demonstration result of sample assay system equipped alternative He-3 detectors

Nakamura, Hironobu; Mukai, Yasunobu; Tobita, Hiroshi; Nakamichi, Hideo; Ozu, Akira; Kureta, Masatoshi; Kurita, Tsutomu; Seya, Michio

Proceedings of 37th ESARDA Annual Meeting (Internet), p.45 - 53, 2015/08

JAEA conducted an R&D project to develop a new type of neutron detector using ZnS/$$^{10}$$B$$_{2}$$O$$_{3}$$ ceramic scintillator (as an alternative neutron detector to He-3) with support of Japanese government. The design of the JAEAs alternative system (ASAS: Alternative Sample Assay System using ceramic scintillator tubes) refers basically to the INVS (INVentory Sample assay system) which is the passive type of neutron assay system equipped total 18 He-3 tubes and capable of measuring the small amount of Pu in the MOX powder or Pu nitrate solution in a vial for nuclear material accountancy and safeguards verification. In order to prove the alternative technology and the performance instead of He-3 detector, and to establish Pu measurement capability, JAEA developed and fabricated ASAS equipped 24 alternative ceramic scintillator tubes (which is equivalent to the same counting efficiency of INVS) and demonstrated. The demonstration activity implemented the confirmation of reproducibility about sample positioning, optimization of detector parameters, counting statistical uncertainty, stability check and figure of merit (FOM) using Cf check source and actual MOX powder in PCDF (Plutonium Conversion Development Facility). In addition, performance comparison between the current INVS and the ASAS was also implemented. In this paper, we present demonstration results with design information with Monte-Carlo simulation code (MCNP).

Journal Articles

Overview of JAEA-ISCN's NDA development programs (for INMM)

Seya, Michio; Koizumi, Mitsuo; Tomikawa, Hirofumi; Naoi, Yosuke; Kureta, Masatoshi; Harada, Hideo; Hajima, Ryoichi; Nakamura, Hironobu

Proceedings of INMM 56th Annual Meeting (Internet), 10 Pages, 2015/07

ISCN of JAEA has conducted (with collaborations with JAEA other centers) the following development programs of advanced NDA technologies since its establishment. (1) Measurement test of the using PNAR-NDA system for Fugen spent fuel assemblies, (2) Basic development of NRF-NDA technologies using LCS $$gamma$$-rays, (3) Development of alternative to $$^{3}$$He neutron detection technology, (4) Development of neutron resonance densitometry. ISCN has just started the following new programs (also with collaborations with JAEA other centers). (5) Demonstration of NRF-non-destructive detection technology for nuclear security using LCS $$gamma$$-rays, (6) Development of active neutron NDA techniques using a pulsed neutron (D-T) source, (7) Feasibility study on monitoring of high active liquid waste in tanks inside cell. This paper presents the results of basic technology development programs already done and introduces above new programs.

Journal Articles

Basic technology development of advanced non-destructive detection / Measurement of nuclear material for nuclear security and nuclear nonproliferation

Seya, Michio; Naoi, Yosuke; Kobayashi, Naoki; Nakamura, Takahisa; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/01

The Integrated Support Center for Nuclear Non-proliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) has been conducting (based on collaborations with JAEA other centers) the following basic technology development programs of advanced non-destructive detection/measurement of nuclear material for nuclear security and nuclear non-proliferation. (1) The demonstration test of the Pu-NDA system for spent fuel assembly using PNAR and SINRD (JAEA/USDOE(LANL) collaboration, completed in JFY2013), (2) Basic development of NDA technologies using laser Compton scattered $$gamma$$-rays (Demonstration of an intense mono-energetic $$gamma$$-ray source), (3) Development of alternative to He-3 neutron detection technology, (4) Development of neutron resonance densitometry (JAEA/JRC collaboration)This paper introduces above programs.

Journal Articles

Development and demonstration of a Pu NDA system using ZnS/$$^{10}$$B$$_{2}$$O$$_{3}$$ ceramic scintillator detectors

Nakamura, Hironobu; Ozu, Akira; Kobayashi, Nozomi*; Mukai, Yasunobu; Sakasai, Kaoru; Nakamura, Tatsuya; Soyama, Kazuhiko; Kureta, Masatoshi; Kurita, Tsutomu; Seya, Michio

Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07

To establish an alternative technique of He-3 neutron detector that is used for nuclear material accountancy and safeguards, we have started an R&D project to develop a new type of neutron detector (Pu NDA system) using ZnS/$$^{10}$$B$$_{2}$$O$$_{3}$$ ceramic scintillator with support of Japanese government. The design of the alternative system (ASAS: Alternative Sample Assay System) is basically referenced from INVS (INVentory Sample assay system) which is passive neutron assay system of plutonium and has total 18 He-3 tubes (about 42% of counting efficiency), and the small amount of Pu in the MOX powder or Pu nitrate solution in a vial can be measured. In order to establish the technology and performance after the fabrication of the new detector progresses, we are planning to conduct demonstration activity in the early 2015 experimentally. The demonstration activity implements the confirmation of reproducibility about sample positioning, optimization of detector parameters, counting statistical uncertainty, stability (temperature and $$gamma$$-ray change) check and figure of merit (FOM) using check source and actual MOX powder. In addition to that, performance comparison between current INVS and the ASAS are also conducted. In this paper, we present some analytical study results using a Monte-Carlo simulation code (MCNP), entire ASAS design and demonstration plan to prove technology and performance.

Journal Articles

Design and implementation of $$^{10}$$B+$$^{3}$$He integrated continuous monitor (BHCM) to holdup monitoring in glove boxes

Mukai, Yasunobu; LaFleur, A. M.*; Nakamura, Hironobu; Menlove, H. O.*; Swinhoe, M. T.*; Marlow, J. B.*; Kurita, Tsutomu

Proceedings of INMM 55th Annual Meeting (Internet), 8 Pages, 2014/07

In order to improve the safeguards and nuclear material accountancy of holdup measurements and establish an alternative technology for $$^{3}$$He shortage, we have designed the $$^{10}$$B + $$^{3}$$He Integrated Continuous Monitor (BHCM) and implemented the measurements to continuously monitor the holup in gloveboxes at Plutonium Conversion Developoment Facility. In this paper, we present the outline of BHCM, the comparison between MCNP simulations and the measured results in preliminaly test and a demonstration of process monitoring ability during operation to see the relation between Totals trend and operational status by using $$^{10}$$B detection tubes.

Journal Articles

Analysis of time evolution of neutron intensity measured with a high-sensitive neutron collar during the JCO criticality accident

Endo, Akira; Yamaguchi, Yasuhiro; Sumita, Kenji*

Journal of Nuclear Science and Technology, 40(8), p.628 - 630, 2003/08

 Times Cited Count:4 Percentile:32.21(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Design and fabrication of flow partition tube with He-3 gas screen for OSF-1

Kanno, Masaru; ; ; ;

JAERI-Tech 97-042, 53 Pages, 1997/09

JAERI-Tech-97-042.pdf:2.17MB

no abstracts in English

Oral presentation

Design and development of a Pu NDA system using alternative He-3 neutron detectors using ceramic scintillator

Ozu, Akira; Kureta, Masatoshi; Kobayashi, Nozomi*; Takase, Misao*; Kurata, Noritaka*; Tobita, Hiroshi; Haruyama, Mitsuo; Nakamura, Tatsuya; Suzuki, Hiroyuki; Sakasai, Kaoru; et al.

no journal, , 

no abstracts in English

Oral presentation

Demand for He-3 neutron detectors in the world and development of the alternative detectors in J-PARC

Sakasai, Kaoru; Nakamura, Tatsuya; To, Kentaro; Soyama, Kazuhiko

no journal, , 

After the simultaneous terrorist attacks on September 11, 2001 in the U.S., the supply for He-3 gas has stagnated. Therefore, development of alternative to the He-3 detectors has been conducted in a large neutron experiment facility such as J-PARC, where a lot of He-3 neutron detectors are required. In this report, the supply for He-3 gas in the world is over-viewed and the development status of the alternative detectors using wavelength-shifting fibers and scintillators in J-PARC is described.

Oral presentation

Performance tests of neutron detector amplifiers for a system using the fast neutron direct interrogation method

Komeda, Masao; Maeda, Makoto; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi; Toh, Yosuke

no journal, , 

no abstracts in English

Oral presentation

Development of fuel transient test facility in JMTR

Kimura, Nobuaki; Matsui, Yoshinori; Tobita, Masahiro*; Nakamura, Jinichi; Yamaura, Takayuki

no journal, , 

Power transient tests for the fuels of light water reactors were to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels had been to be investigated by the tests. Prior to the irradiation tests of the fuels, evaluation of thermal-hydraulic behavior in the capsule using ACE-3D code were carried out. And more, the out-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. From these analytical and experimental results, it was confirmed that the power ramping tests for 10$$times$$10 BWR fuel are able to achieve linear heat rate of 600W/cm in JMTR.

Oral presentation

Developing delayed gamma-ray spectroscopy for reprocessing plant nuclear safeguards; Neutron detection system development

Lee, H.-J.; Rodriguez, D.; Rossi, F.; Koizumi, Mitsuo; Takahashi, Tone

no journal, , 

13 (Records 1-13 displayed on this page)
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