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Journal Articles

Development of NRD, 3; Study of a new moderator for compact 14-MeV pulsed neutron sources

Takamine, Jun; Koizumi, Mitsuo; Kureta, Masatoshi; Harada, Hideo; Kitatani, Fumito; Tsuchiya, Harufumi; Seya, Michio; Iimura, Hideki

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2015/01

A prototype device of neutron resonance densitometry (NRD) with a D-T neutron generator was planned for basic studies of actual NRD devices. D-T neutron generators had features of simple handling and compact compared with photo neutron sources driven by electron beam accelerators. But those of D-T neutron are higher energy and lower intensity than those of photo neutron. We designed a new type moderator to compensate for the shortcomings. In the new type moderator, the D-T neutron generator is surrounded by Lead, and Polyethylene is arranged in the beam direction on the surface of Lead. As the result of analysis using Monte Carlo code MCNP5, it was found that the new moderator achieved about four times larger production of low energy neutrons than polyethylene moderator without distorting the energy resolution below at least 100 eV. The lead part in the new moderator are changed to other heavy metals, which is Uranium, and Tungsten. Analysis like the above were performed. We report these results.

Journal Articles

Development of NRD, 2; Investigation on systematic effects due to sample thickness for areal density derived from NRTA

Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Takamine, Jun; Kureta, Masatoshi; Iimura, Hideki; Kimura, Atsushi; Becker, B.*; Kopecky, S.*; et al.

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

We are developing neutron resonance densitometry that combines neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis. The aim is to establish a non-destructive technique that can quantify nuclear materials in particle-like debris of melted fuel resulting from severe nuclear accidents like the one at the Fukushima Daiichi Nuclear Power Plant. Systematic effects due to sample thickness and mixed sample for the areal density measurement by NRTA were investigated at a neutron time-of-facility GELINA, IRMM. The experiments were conducted utilizing natural Cu metal discs with different thickness and a B$$_{4}$$C disc. Areal densities were derived with a resonance shape analysis code REFIT. It was found that they were inconsistent with those calculated by mass and area, when using recommended resonance parameters. Hence, a neutron width of resonance parameters was newly evaluated with the NRTA data and we found that derived areal density agreed within 2% with the expected ones. We also discuss the impacts of mixed sample for the areal density derived from NRTA measurement.

Journal Articles

Development of NRD, 1; Developments of a LaBr$$_{3}$$ scintillation detector system for neutron resonance densitometry

Koizumi, Mitsuo; Tsuchiya, Harufumi; Kitatani, Fumito; Harada, Hideo; Takamine, Jun; Kureta, Masatoshi; Seya, Michio; Kimura, Atsushi; Iimura, Hideki; Becker, B.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2015/01

We have proposed neutron resonance densitometry (NRD) as a method to quantify special nuclear materials in particle-like debris of melted fuel. NRD is a combination of neutron resonance transmission analysis (NRTA), and neutron resonance capture analysis (NRCA) (and prompt $$gamma$$-ray analysis (PGA)). NRCA/PGA is used to identify contaminant elements, which is difficult to be detected by NRTA. To observe $$gamma$$ rays emitted in neutron capture reaction, a spectrometer consisting of LaBr$$_3$$ scintillation detectors has been constructed. A newly installed data acquisition system enables us to measure 500 k event/s for each 8-channel inputs. In this presentation, the research and development of NRD is introduced and the status of the development of the spectrometer system is given as well.

Journal Articles

Approaches to characterization of nuclear material for establishment of nuclear forensics

Okazaki, Hiro; Sumi, Mika; Sato, Mitsuhiro; Kayano, Masashi; Kageyama, Tomio; Martinez, P.*; Xu, N.*; Thomas, M.*; Porterfield, D.*; Colletti, L.*; et al.

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

The quality control section of Plutonium Fuel Development Center (PFDC) in Japan Atomic Energy Agency has been analyzing isotopic compositions and content of plutonium and uranium as well as impurity and physics of nuclear materials in the process of MOX fuel fabrication for accountancy purpose as well as process control purposes. These analytical techniques are also effective for nuclear forensics to identify the source, history, and route of the material by determining a composition and chemical property of it. Therefore, PFDC cooperates with Los Alamos National Laboratory which has broad experience and established measurement skill for nuclear forensics, and evaluates the each method, procedure, and analytical data toward R&D of characterizing a nuclear fuel for forensics purposes. This paper describes the approaches to develop characterization techniques of nuclear fuel for nuclear forensic purpose at PFDC.

Journal Articles

Improvement of INVS measurement uncertainty for Pu nitrate solution

Makino, Risa; Swinhoe, M. T.*; Suzuki, Hisanori; Ikeda, Atsushi*; Menlove, H. O.*; Shimizu, Yasuyuki; Nakamura, Hironobu

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

The Inventory Verification Sample system (INVS) is a non-destructive assay system for samples to quantify the Pu amount in Pu nitrate solutions and MOX with 31.3% of counting efficiency. It has been used for IAEA verification measurement for many years at the Plutonium Conversion Development Facility for the samples taken at the timing of PIV etc. as a partial defects verification system (uncertainty: about 3-5%). If the measurement uncertainty can be improved (to $$sim$$1%), it is expected that the usage can be extended to the operator's own measurements in MC&A to reduce the number of destructive analyses. In order to improve the measurement uncertainty for solution samples, after optimization of detector parameter and sample position, we conducted 3 different types of calibration method that is passive calibration curve, known-$$alpha$$ and multiplicity method to achieve the target uncertainty. To perform calibration and control the measurement quality, MOX fuel pellets with known Pu amount are fabricated and used. In the range of concentration of typical solution samples, we could confirm good correlations between measured doubles and $$^{240}$$Pu effective mass in the three methods. Especially, it was confirmed that the conventional calibration curve method could meet our target uncertainty ($$sim$$1%).

Journal Articles

Status of $$gamma$$-ray nondestructive assay by laser Compton scattered source

Hajima, Ryoichi; Shizuma, Toshiyuki; Nagai, Ryoji; Mori, Michiaki; Hayakawa, Takehito; Angell, C.; Seya, Michio

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2015/01

no abstracts in English

Journal Articles

Development of human resource capacity building assistance for nuclear security

Nakamura, Yo; Noro, Naoko

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2015/01

The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) has been providing nuclear security human resource development projects targeting at nuclear emerging countries in Asia in cooperation with the authorities concerned including the Sandia National Laboratory (SNL) and the International Atomic Energy Agency (IAEA). In the aftermath of the attacks of Sept. 11, the threat of nuclear security was internationally recognized and thus the human resource capacity building is underway as an urgent task. In order to responding to emerging threats, the human resource capacity building that ISCN has implemented thus far needs to be multilaterally analyzed in order to develop more effective training programs. This paper studies ISCN's future direction by analyzing its achievements, as well as introduces the collaborative relationships with SNL that contributes to the reflection and maintenance of international trends for the contents of nuclear security training, the nuclear security enhancement support with which Japan is to provide nuclear emerging countries in Asia, and the achievements of the nuclear security training program that ISCN implemented.

Journal Articles

Tabletop exercise as a tool of evaluating physical protection system

Matsuzawa, Reina

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

Evaluation of designed and implemented physical protection system (PPS) is essential for ensuring the effectiveness of PPS. In Japan, based on its national law requiring performance-based assessment of PPS, nuclear facility operators have conducted performance test of PPS element and periodical trainings as well as annual PPS exercise with relevant agencies. In addition to these practical or field efforts, non-field tool for evaluating PPS effectiveness such as tabletop exercise (TTX) can be utilized as it is applied in the USA and other countries. This paper discusses the potential advantage of TTX as an evaluation tool of PPS effectiveness, looking at the characterizations of TTX in comparison to field evaluations, and potential cases where operator would get benefit from TTX especially.

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) Nippon 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

Evaluating methods to improve safeguards training courses of ISCN

Okumura, Yukiko; Nakamura, Yo; Kawata, Norio

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2015/01

Although questionnaires were used to receive feedbacks from participants at the end of each training course, Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) did not establish a structured evaluation method. To this end, ISCN has started to study on methods to accurately evaluate the courses since April and started to introduce the evaluation method on trial, according to the Donald Kirkpatrick's Four-Level Training Evaluation Model, so as to better develop and conduct more effective courses. This paper will focus on how ISCN has modified the Kirkpatrick's Four-level to adapt to its safeguards training courses. This will then be followed by two particular cases of how the evaluation method functioned for the Additional Protocol training courses held in Malaysia in 2014, and the feedbacks received to improve future training courses.

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