Journal of nuclear science and technology = 日本原子力学会英文論文誌

• 資料種別: 雑誌
• ISSN: 0022-3131
• ISSN-L: 0022-3131
• タイトル: Journal of nuclear science and technology
• タイトルよみ: Journal of nuclear science and technology
• 巻次・部編番号: 48(5)-48(12):2011.5-2011.12
• 著者標目: 日本原子力学会 ニホン ゲンシリョク ガッカイ ( 00280990 )典拠
• 出版事項: Tokyo : Atomic Energy Society of Japan
• 出版年月日等: 2011
• 出版年（W3CDTF）: 2011
• 刊行巻次・年月次: 1(1):1964.4 -
• 大きさ: 26-30cm
• 並列タイトル等: 日本原子力学会英文論文誌 ニホン ゲンシリョク ガッカイ エイブン ロンブンシ
• 出版地（国名コード）: JP
• 本文の言語コード: eng
• NDLC: ZM35
• 一般注記: Description based on the latest issue
• 所蔵機関: 国立国会図書館
• 請求記号: Z53-A460
• 関連情報: 区分換; https://ndlsearch.ndl.go.jp/books/R100000002-I024068116
• 連携機関・データベース: 国立国会図書館 : 国立国会図書館蔵書; https://ndlsearch.ndl.go.jp
• 書誌ID（NDLBibID）: 000000118776; http://id.ndl.go.jp/bib/000000118776
• 全国書誌番号: 10010902
• 目録規則: 国立国会図書館逐次刊行物目録規則
• 整理区分コード: 132

目次

Fukushima NPP accident related: Analysis of core melt accident in Fukushima Daiichi-Unit 1 nuclear reactor

Application of organic photodiodes to X-ray measurements: a feasibility study

Measurement of charged-particle emission double-differential cross section of fluorine for 14.2 MeV neutrons

Fading characteristics of alpha radiation signals stored in an imaging plate

On effective delayed neutron fraction calculations with interated fission probability

Adsorption of Molybdenum Hexafluoride on Magnesium Difluoride for Uranium Purification in FLUOREX Reprocessing

Features of Dendritic Oxide during Sodium Combustion

Gamma-Ray-Driven Photovoltaic Cells via a Scintillator Interface

Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations

Adjoint Sensitivity and Uncertainty Analyses in Monte Carlo Forward Calculations

Separation of trivalent minor actinides from fission products using single R-BTP column extraction chromatography

A thermoelectric-conversion power supply system using a strontium heat source of high-level radioactive nuclear waste

Mitigation technologies for damage induced by pressure waves in high-power mercury Spallation Neutron Sources (3) Consideration of the effect of microbubbles on pressure wave propagation through a water test

Determination of subcritical reactivity of a thermal accelerator-driven system from beam trip and restart experiment

Effect of tritium and dissolved oxygen on anodic polarization of SUS304 stainless steel in sulfuric acid solution

Fukushima NPP accident related: Preliminary numerical experiments on oceanic dispersion of 131I and 137Cs discharged into the ocean because of the Fukushima Daiichi nuclear power plant disaster

Analysis of n + 6Li reactions using the continuum-discretized coupled-channels method

Thermal performance of intermediate heat exchanger during high-temperature continuous operation in HTTR

Ring compression ductility of high-burnup fuel cladding after exposure to simulated LOCA conditions

Advantages of response function change in a transXend detector with various scintillators as substrates of segment detectors

Evaluation of proliferation resistance of plutonium based on decay heat

Basic analysis on isotopic barrier of material attractiveness based on plutonium composition of FBR

Bubble growth rates and nucleation site densities in saturated pool boiling of water at high pressures

Measurement of keV-neutron capture cross section of 96Zr

Distribution and characteristics of radon gas in soil from a high-background-radiation city in China

Adsorption characteristics of trivalent rare earths and chemical stability of a silica-based macroporous TODGA adsorbent in HNO3 solution

Experimental study on wave propagation behavior on free surface of lithium flow for IFMIF

Neutron nuclear data evaluation of cesium isotopes for JENDL-4.0

Applied moving-temperature-gradient technique for CsI(Tl) crystal growth

Effects of crew resource management training on the team performance of operators in an advanced nuclear power plant

Fukushima NPP accident related: Removal of cesium using cobalt-ferrocyanide-impregnated polymer-chain-grafted fibers

Application of data reconciliation and gross error detection to nuclear material accounting for spent fuel reprocessing

LOCA analysis of super fast reactor

3D simulation of solid-melt mixture flow with melt solidification using a finite volume particle method

Extraction of Am(3) at the interface of organic-aqueous two-layer flow in a microchannel

Impact of revised thermal neutron capture cross section of carbon stored in JENDL-4.0 on HTTR criticality calculation

Establishment of voluntary consensus codes and the role of code engineers: example of creating the environmental fatigue evaluation method for light water reactors

Nuclear level densities with microscopic statistical method using a consistent residual interaction

Solubility and solubility-limiting solid phase in M(4)-OH-dicarboxylate ternary aqueous system

Noncondensable gas accumulation phenomena in nuclear power plant piping