Class information for: |
Basic class information |
ID | Publications | Average number of references |
Avg. shr. active ref. in WoS |
---|---|---|---|
5293 | 1577 | 22.0 | 35% |
Classes in level above (level 2) |
ID, lev. above |
Publications | Label for level above |
---|---|---|
1123 | 9210 | JOURNAL OF NUCLEAR MATERIALS//NUCL MAT SCI//OXIDE DISPERSION STRENGTHENED STEEL |
Terms with highest relevance score |
Rank | Term | Type of term | Relevance score (tfidf) |
Class's shr. of term's tot. occurrences |
Shr. of publ. in class containing term |
Num. of publ. in class |
---|---|---|---|---|---|---|
1 | IRRADIATION ASSISTED STRESS CORROSION CRACKING | Author keyword | 13 | 51% | 1% | 18 |
2 | RADIATION INDUCED SEGREGATION | Author keyword | 13 | 40% | 2% | 25 |
3 | REDUCED RADIOACTIVATION MATERIALS | Author keyword | 6 | 100% | 0% | 4 |
4 | IASCC | Author keyword | 3 | 32% | 1% | 9 |
5 | COMMERCIAL NUCL FUEL | Address | 3 | 100% | 0% | 3 |
6 | IRRADIATION INDUCED SEGREGATION | Author keyword | 3 | 50% | 0% | 4 |
7 | DEN DANS DMN SEMI | Address | 3 | 60% | 0% | 3 |
8 | RADIATION INDUCED PRECIPITATION | Author keyword | 3 | 60% | 0% | 3 |
9 | CONSTANT EXTENSION RATE TENSILE TESTS | Author keyword | 2 | 67% | 0% | 2 |
10 | DAMAGING DOSE | Author keyword | 2 | 67% | 0% | 2 |
Web of Science journal categories |
Author Key Words |
Key Words Plus |
Rank | Web of Science journal category | Relevance score (tfidf) |
Class's shr. of term's tot. occurrences |
Shr. of publ. in class containing term |
Num. of publ. in class |
---|---|---|---|---|---|
1 | RADIATION INDUCED SEGREGATION | 39 | 45% | 4% | 65 |
2 | FE CR MN | 17 | 100% | 1% | 8 |
3 | CR NI ALLOYS | 15 | 30% | 3% | 43 |
4 | OVERSIZED ELEMENTS | 11 | 69% | 1% | 9 |
5 | IRRADIATION CREEP | 10 | 29% | 2% | 28 |
6 | INDUCED SOLUTE SEGREGATION | 9 | 83% | 0% | 5 |
7 | BN 350 REACTOR | 8 | 100% | 0% | 5 |
8 | AUSTENITIC ALLOYS | 8 | 42% | 1% | 14 |
9 | CONCENTRATED ALLOYS | 6 | 43% | 1% | 10 |
10 | LOW DISPLACEMENT RATES | 6 | 100% | 0% | 4 |
Journals |
Reviews |
Title | Publ. year | Cit. | Active references |
% act. ref. to same field |
---|---|---|---|---|
Radiation-induced degradation of stainless steel light water reactor internals | 2012 | 13 | 48 | 79% |
A REVIEW OF IRRADIATION ASSISTED STRESS-CORROSION CRACKING | 1994 | 118 | 10 | 60% |
A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels | 2011 | 14 | 7 | 86% |
Micromechanics of dislocation channeling in intergranular stress corrosion crack nucleation | 2012 | 11 | 29 | 45% |
A review of irradiation effects on LWR core internal materials - Neutron embrittlement | 2011 | 9 | 24 | 58% |
MICROSTRUCTURAL EVOLUTION IN ANNEALED AUSTENITIC STEELS DURING NEUTRON-IRRADIATION | 1987 | 58 | 23 | 48% |
Observation of point defect production and clustering by high voltage electron microscopy: Interaction of point defect with solutes | 1996 | 5 | 12 | 58% |
Challenges to the use of ion irradiation for emulating reactor irradiation | 2015 | 0 | 59 | 42% |
RECENT RESEARCH-AND-DEVELOPMENT OF REDUCED ACTIVATION FERROUS MATERIALS IN JAPAN | 1990 | 3 | 11 | 64% |
RECENT PROGRESS IN FUSION-REACTOR MATERIALS STUDIES - FOCUS ON TRANSMUTATION AND RADIOACTIVATION ASPECTS | 1993 | 2 | 37 | 59% |
Address terms |
Rank | Address term | Relevance score (tfidf) |
Class's shr. of term's tot. occurrences |
Shr. of publ. in class containing term |
Num. of publ. in class |
---|---|---|---|---|---|
1 | COMMERCIAL NUCL FUEL | 3 | 100% | 0.2% | 3 |
2 | DEN DANS DMN SEMI | 3 | 60% | 0.2% | 3 |
3 | ASSOC EURATOM FESTKORPERFOR | 1 | 50% | 0.1% | 2 |
4 | MAT INTER ES CHARACTERIZAT GRP | 1 | 100% | 0.1% | 2 |
5 | RD MMC | 1 | 50% | 0.1% | 2 |
6 | MAT OURCES | 1 | 12% | 0.6% | 9 |
7 | ADV MAT KITA KU | 1 | 50% | 0.1% | 1 |
8 | DMN SRMA LC2M | 1 | 50% | 0.1% | 1 |
9 | ENGN NUCL EQUIPMENT STRENGTH RELIABIL LIFET | 1 | 50% | 0.1% | 1 |
10 | GRP REACTOR STRUCT MAT | 1 | 50% | 0.1% | 1 |
Related classes at same level (level 1) |
Rank | Relatedness score | Related classes |
---|---|---|
1 | 0.0000254031 | HIGH MN CR STEEL//IN SITU IRRADIATION EFFECT//INSITU IRRADIATION TEST |
2 | 0.0000173720 | NUCL MAT SCI//FRONTIER ULTRA HIGH SPEED PLAST DEFO//POINT DEFECT CLUSTERS |
3 | 0.0000150149 | MERCURY TARGET//PROJEKT ESS//ENGN CSNS TARGET STN RUMENTS |
4 | 0.0000148945 | OXIDE DISPERSION STRENGTHENED STEEL//ODS STEEL//ODS FERRITIC STEEL |
6 | 0.0000137483 | HE VACANCY CLUSTER//HELIUM BUBBLE//PI3 TM |
7 | 0.0000089201 | GAS SAMPLES//INTERSTITIAL IMPURITY ATOM//MAGNETIC RESONANCE MASS SPECTROMETER |
8 | 0.0000080496 | VANADIUM ALLOY//INT NUCL MAT SCI//V 5CR 5TI ALLOY |
9 | 0.0000080425 | IRON NEODYMIUM BORON ALLOY//RADIATION INDUCED AMORPHIZATION//ZIRCONIUM BASED ALLOY |
10 | 0.0000078100 | SECT PL MET//CARRERA INVEST//ULTRA FAST DIFFUSION |