Search Results 1-20 of 90

1
2
3
4
5
1 / 5

1

Neutronics Assessment of a Compact D-D Neutron Generator as a Neutron Source for the Neutron Calibration in Magnetic Confinement Fusion Devices

NISHITANI Takeo , RODIONOV Roman , KRASILNIKOV Vitaly , SAXENA Aakanksha , CORE Laura , BERTALOT Luciano

… The neutron emission distribution of the compact D-D neutron generator has a large anisotropy not only due to the scattering with the neutron generator body but also due to the intrinsic anisotropy of the differential cross-section of the d(d,n)3He reaction. …

Plasma and Fusion Research 15(0), 2402017-2402017, 2020

J-STAGE
2

VALIDATION OF GRAPHITE CROSS SECTION IN VARIOUS INTEGRAL EXPERIMENTS

Peltan Tomáš , Košťál Michal , Prehradný Jan , Schulc Martin , Dostál Václav

… Data obtained from measurement of neutron leakage spectrum with 252Cf in graphite cube center can be proposed for such kind of adjustments. …

The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2083, 2019

J-STAGE
3

A Radioisotope Neutron Source and its Application for Dosimetry [in Japanese]

Kowatari Munehiko

… Only 241Am-Be and 252Cf neutron sources are now available due to reliable reproducibility of neutron emission, long half-lives and less disturbing gamma ray emission. …

hamon 27(3), 109-112, 2017

J-STAGE
4

Quantification of capture reaction of structual material in subcritical system by gamma ray measurement:Estimation of Al(n,gamma) reaction rates in KUCA-C core [in Japanese]

Nauchi Yasushi , Takanori Kameyama , Hironobu Unesaki , Tsuyoshi Misawa , Tasafumi Sano , Takahiro Yagi

… 京都大学臨界集合体実験装置でウラン-アルミニウム合金燃料板と軽水減速材、ステンレス鋼性の下部格子板からなる複数の未臨界炉心を構成し、その炉中心に252Cf中性子源を装荷し、炉外に配置したBGO検出器でγ線を測定した。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012f(0), 156, 2012

J-STAGE
5

Shape of Neutron Energy [in Japanese]

Nohtomi Akihiro

… A notable and interesting signal enhancement due to recoil protons generated in an acrylic converter was observed on IP images for irradiation with a 252Cf source. …

Japanese Journal of Medical Physics (Igakubutsuri) 32(3), 130-137, 2012

J-STAGE Ichushi Web
6

Microdosimetry on a Mini-Reactor UTR-KINKI for Educational Uses and Biological Researches

ENDO Satoru , TANAKA Kenichi , FUJIKAWA Kazuo , HORIGUCHI Tetsuo , ITOH Tetsuo , ONIZUKA Yoshihiko , HOSHI Masaharu , MURATAKA Ayanori , KOJIMA Yasuaki , SHIZUMA Kiyoshi

… The averaged lineal energy for neutron was slightly larger than that of the fission neutrons from 252Cf, and the averaged lineal energy for gamma-ray had similar site-size-dependence of 25 keV gamma-rays and 250 kV X-rays. …

Journal of Radiation Research 50(1), 83-87, 2009-01-16

J-STAGE NDL Digital Collections Ichushi Web References (15)
7

Development of Landmine Detection System by using Backscattering Neutrons (II)

Subkhi Mohamad Nurul , Takahashi Yoshiyuki , Yagi Takahiro , Misawa Tsuyoshi , Pyeon Cheol Ho , Shiroya Seiji

… In numerical simulations, 252Cf neutron source position and reflector dimensions are optimized for examination of determination mimic explosive (melamine; … The difference between 3He(n,p) reaction rates with and without melamine by MCNP is investigated in the energy range of thermal and fast neutrons. …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2009f(0), 111-111, 2009

J-STAGE
8

Development of New Group Constants Library "SFCX-J33" for Radiation Shielding Analysis of Spent Fuel Transport Cask:(2)Benchmark Experiment using 252Cf Fission Neutoron Source and its Analysis [in Japanese]

Ohnishi Seiki , Nakata Mikihiro , Odano Naoteru , Morishima Makoto , Omura Masaki , Sawada Ken-ichi , Konnai Akiko , Asami Mitsufumi

… 252Cf中性子源を用いた中性子及び即発・二次ガンマ線遮へい透過実験を平板体系及び輸送容器を模擬した輸送容器体系で行った。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2009s(0), 89-89, 2009

J-STAGE
9

Imaging Mass Spectrometry with Swift Heavy Ions [in Japanese]

NAKATA Yoshihiko , YAMADA Hideaki , HONDA Yoshiro , NINOMIYA Satoshi , SEKI Toshio , AOKI Takaaki , MATSUO Jiro

… Desorption of large biomolecular ions due to irradiation by swift heavy ions was first observed in 1974, and the time-of-flight mass spectrometry using fission fragments from a 252Cf source is called plasma desorption mass spectrometry (PDMS). …

Journal of the Mass Spectrometry Society of Japan 56(4), 201-208, 2008-08-01

J-STAGE References (25)
10

Neutron Dose Rate in the Facility at the Cyclotron Center of Chung Shan Medical University

LEE Jui-Ping , CHEN Chien-Yi

… This system was calibrated using two 252Cf neutron sources and simulated according to MCNP code. … The results show various DRs up to 120 μSv h-1 …

Journal of Radiation Research 49(2), 147-151, 2008-03-15

J-STAGE NDL Digital Collections Ichushi Web References (13) Cited by (1)
11

Neutron Measurement using Magnetically Levitated Electrode Ionization Chamber [in Japanese]

KAWAGUCHI TOSHIRO , KORENAGA KAZUHITO , ICHIKI HIROFUMI , WAKABAYASHI GENICHIRO , ISHIBASHI KENJI , UTSUNOMIYA YOSHITOMO

… ガドリニウム装置型磁気浮上電極電離箱を開発し、中性子（線源：252Cf）の線量当量率を測定した。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2008s(0), 99-99, 2008

J-STAGE
12

Development of application of gadolinium compounds to thin film scintillators:(4) - An attempt of measuring neutron - [in Japanese]

Haruna Jun , Furusaka Michihiro , Kiyanagi Yoshiaki , Kaneko Junichi , Higuchi Mikio , Kawamura Souhan , Saeki Syohei , Yagi Yasuhiro , Ishibashi Hiroyuki , Fujita Fumiyuki , Homma Akira

… Gd2Si2O7(GPS)の252Cfからの中性子に対する応答測定を行った結果、GPSはGd2SiO5(GSO)の約3倍の発光を示した。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2007f(0), 99-99, 2007

J-STAGE
13

Development and Characterization of Neutron Calibration Field Simulating the MOX Fuel Plant (4):Improvement of Accuracy of Neutron Spectra and Reference Dose Rate

YOSHIDA Tadayoshi , TSUJIMURA Norio

MOX燃料施設の作業環境を模擬した減速中性子校正場の中性子スペクトル及び基準線量率の評価において，MCNPによる計算における照射室の壁・床のコンクリート組成情報の見直しや中性子スペクトロメータによる繰り返し測定等を行い，計算値と測定値との一致度の向上を図った。

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2006s(0), 642-642, 2006

J-STAGE
14

Statistical Model Calculaiton of Fission Neutron Spectrum

Iwamoto Osamu

… Hauser-Feshbach統計モデルに基づき、核分裂片からの即発中性子及びガンマ線放出の計算を行い、252Cfの自発核分裂からの中性子放出スペクトルの結果を実験データと比較した。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2006s(0), 46-46, 2006

J-STAGE
15

Anisotropic Fluence Distribution in 252Cf Neutron Calibration Field Due to Scattering from Support Structure [in Japanese]

TSUJIMURA Norio , YOSHIDA Tadayoshi

… 252Cf standard source. … 252Cf doubly-encapsulated in a welded stainless steel (AEA Technology QSA, Xl capsule) . …

RADIOISOTOPES 55(2), 61-70, 2006

J-STAGE
16

Development of a Heat-Resistant Neutron Shielding Resin for the National Centralized Tokamak

MORIOKA Atsuhiko , SAKURAI Shinji , OKUNO Koichi , TAMAI Hiroshi

… The neutron shielding performance of the developed resin, which was examined by usinga 252Cf neutron source, was almost identical to that of polyethylene. …

Journal of Plasma and Fusion Research 81(9), 645-646, 2005-09-25

J-STAGE NDL Digital Collections References (6)
17

Neutron Dose Assessment Using Ebonite in Criticality Accidents [in Japanese]

TSUJIMURA Norio , MIKAMI Satoshi , YOSHIDA Tadayoshi , TAKADA Chie

… A disc-shaped ebonite, a hard rubber containing 30wt% sulfur, can be used as a highly effective criticality neutron dosemeter because of a simplicity of measurements of beta activity arising from 32S(n, p)32P reactions. …

Japanese Journal of Health Physics 40(3), 267-276, 2005-09-01

J-STAGE Ichushi Web References (15)
18

Development and Characterization of Neutron Calibration Field Simulating the MOX Fuel Plant (3):Characteristics of Neutron Dosemeters

Takada Chie , Tsujimura Norio , Yoshida Tadayoshi

… 252Cf中性子線源と鉄，PMMAなどの減速材の組み合わせにより実現した減速中性子校正場においてMOX燃料施設の作業環境を模擬し，レムカウンタ及び個人線量計のレスポンスのエネルギー特性を評価した。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2005s(0), 666-666, 2005

J-STAGE
19

Characteristics of a neutron calibration field with a D2O-moderated 252Cf source

Takahashi Masa , Kowatari Munehiko , Shimizu Shigeru , Yoshizawa Michio

… 重水減速材付252Cf線源を用いた中性子校正場は、核燃料施設の実作業環境に漏洩する中性子線場に近いエネルギースペクトルを持つ校正場としてISO8529-1で推奨されている。 …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2005s(0), 668-668, 2005

J-STAGE
20

Development of Simple Passive Neutron Dosimeter with Cylindrical Acrylic Resin Moderator Using Thermoluminescent Detector [in Japanese]

OGAWA Yoshihiro , SENOO Takafumi

… : Tm+6LiF and … : Tm+7LiF, as a thermal neutron detector, was produced. … 252Cf and … In addition, the response function of neutron dosimeter from 10-9 …

RADIOISOTOPES 54(8), 287-295, 2005

J-STAGE

1
2
3
4
5
1 / 5

Search Results 1-20 of 90

Related Authors

Related Journals