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: 45(7)-45(12):2008.7-2008.12(P.589-1352)
• 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: 2008
• Publication Date (W3CDTF): 2008
• 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

Aqueous dissolution of silver iodide and associated iodine release under reducing conditions with FeCl2 solution

Neutron irradiation effect on isotopically tailored 11B4C

Thermal-hydraulic analysis for inversely stratified molten corium in lower vessel

Recovery of metals from simulated high-level radioactive waste glass through phase separation

Long-term integrity of waste package final closure for HLW geological disposal (5) Applicability of MAG welding method to overpack final closure

Application of Monte Carlo method to solve the neutron kinetics equation for a subcritical assembly

Nuclear criticality safety evaluation of a mixture of MOX, UO2 and additive in the most conservative concentration distribution

Evaluation methods for corrosion damage of components in cooling systems of nuclear power plants by coupling analysis of corrosion and flow dynamics (1) Major targets and development strategies of the evaluation methods

Development of three-dimensional numerical model for 222Rn and its decay products coupled with a mesoscale meteorological model (2) Numerical analysis on the increase in gamma dose rate observed in the coastal area of Fukushima Prefecture

Application of the comprehensive sensitivity analysis method to a Korean geological disposal concept

Breeding capability and void reactivity analysis of heavy-water-cooled thorium reactor

An approach to reuse of PCB-contaminated transformer oil using gamma radiolysis: basic decomposition property of PCB and 1,2,4-trichlorobenzene under gamma ray irradiation

Effect of sodium nitrate on the diffusion of Cl[-] and I[-] in compacted bentonite

Engineering design of a high-capacity vol-oxidizer for handling UO2 pellets of tens of kilogram

Error estimation of values obtained from practical CFD analysis

Pandemonium problem in fission-product decay heat calculations revisited

Discrete fragment model for complex formation of europium(3) with humic acid

In-core SCC growth behavior of type 304 stainless steel in BWR simulated high-temperature water at JMTR

Hydrolysis constant and coordination geometry of zirconium(4)

Whole core transport calculation employing hexagonal modular ray tracing and CMFD formulation

Lifetime estimation of microbubble in mercury

Effect of subchannel void fraction distribution on lattice physics parameters for boiling water reactor fuel bundles

Analysis of reverse flow in inverted U-tubes of steam generator under natural circulation condition

Numerical simulation on effect of methanol addition on coolant radiolysis in pressurized water reactor

Evaluation methods for corrosion damage of components in cooling systems of nuclear power plants by coupling analysis of corrosion and flow dynamics (2) Evaluation of corrosive conditions in PWR secondary cooling system

Corrosion behavior of stainless steels in simulated PWR primary water: effect of chromium content in alloys and dissolved hydrogen

Development of axially simplified method of characteristics in three-dimensional geometry

Applicability of the diffusion and simplified P3 theories for pin-by-pin geometry of BWR

Radiation dose as a barrier against proliferation for advanced fuel compositions

Feasibility of reprocessed uranium in LWR fuel cycle for protected plutonium production