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

• Material Type: 雑誌
• Title: Journal of nuclear science and technology
• Title Transcription: Journal of nuclear science and technology
• Volume: 47(7)-47(12):2010.7-2010.12(P.575-1232)
• Author Heading: 日本原子力学会 ニホン ゲンシリョク ガッカイ ( 00280990 )Authorities
• Publication, Distribution, etc.: Tokyo : Atomic Energy Society of Japan
• Publication Date: 2010
• Publication Date (W3CDTF): 2010
• Year and volume of publication: 1(1):1964.4 -
• Size: 26-30cm
• Alternative Title: 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
• ISSN (Periodical Title): 0022-3131
• ISSN-L (Periodical Title): 0022-3131
• Place of Publication (Country Code): JP
• Text Language Code: eng
• NDLC: ZM35
• Note (General): Description based on the latest issue
• Holding library: 国立国会図書館
• Call No.: Z53-A460
• Related Material: 区分換; https://ndlsearch.ndl.go.jp/books/R100000002-I024068116
• Data Provider (Database): 国立国会図書館 : 国立国会図書館蔵書; https://ndlsearch.ndl.go.jp
• Bibliographic ID (NDL): 000000118776; http://id.ndl.go.jp/bib/000000118776
• Cataloging Rule: National Diet Library Cataloging Rules for Serials

Table of Contents

Special issue on NTHAS6

Improvement of gas entrainment prediction method: introduction of surface tension effect (Special issue on NTHAS6)

A continuity-based semi-implicit scheme for transient two-phase flows (Special issue on NTHAS6)

Thermal mixing in T-junction piping system related to high-cycle thermal fatigue in structure (Special issue on NTHAS6)

Parametric analysis of the axial nodal size in a faster-running DNBR program (Special issue on NTHAS6)

Distribution of microbubble sizes and behavior of large bubbles in mercury flow in a mockup target model of J-PARC

Denaturing generated Pu in fast breeder reactor blanket

Assessment of FBR MONJU accident management reliability in causing reactor trips

Development of a method to calculate k[eff] satisfying a convergence criterion of source iteration in Monte Carlo calculation

Effect of sample moisture and bulk density on performance of the 241Am-Be source based Prompt Gamma rays Neutron Activation Analysis setup: a Monte Carlo study

Increase in irradiation beam intensity by using a hybrid target system in cyclotron-based neutron capture therapy

Wear prediction of steam generator tubes due to shell side foreign objects

Interpolation and extrapolation method to analyze irradiation-induced dimensional change data of graphite for design of core components in Very High Temperature Reactor (VHTR)

Simple electrolyzer model development for high-temperature electrolysis system analysis using solid oxide electrolysis cell

Characteristics of bubble departure frequency in a low-pressure subcooled boiling flow

Closed chamber salt distillation system for an enhanced recovery of evaporated pure salt

Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method

Behavior of coated fuel particle of high-temperature gas-cooled reactor under reactivity-initiated accident conditions

Strength degradation of oxidized graphite support column in VHTR

A study on hydraulic properties of compacted Fe(3)-montmorillonite

Measurement of neutron capture cross section ratios of 244Cm resonances using NNRI

Impact of partitioning and transmutation on high-level waste disposal for the fast breeder reactor fuel cycle

Assessment of applicability of two-fluid model code ACE-3D to heat transfer test of supercritical water flowing in an annular channel

Development of spectral history and pin power correction methods for pin-by-pin core analysis method using three-dimensional direct response matrix

Probabilistic fracture mechanics round robin analysis of reactor pressure vessels during pressurized thermal shock

Protected Plutonium Production by transmutation of minor actinides for peace and sustainable prosperity: irradiation tests of Np and Np-U samples in the experimental fast reactor JOYO (JAEA) and the advanced test reactor at INL

Role of best estimate plus uncertainty methods in major nuclear power plant modifications

Study of the self-controllability for the fast reactor core with high-thermal-conductivity fuel

Development of a suppression method for deposition of radioactive cobalt after chemical decontamination (2) Consideration of Fe3O4 plating mechanism on stainless steel in aqueous solution at 363K

A stochastic approach to monoenergetic space-time nuclear reactor kinetics