Class information for: |
Basic class information |
Class id | #P | Avg. number of references |
Database coverage of references |
---|---|---|---|
7884 | 1317 | 20.5 | 29% |
Hierarchy of classes |
The table includes all classes above and classes immediately below the current class. |
Cluster id | Level | Cluster label | #P |
---|---|---|---|
18 | 4 | THERMODYNAMICS//ENERGY & FUELS//ENGINEERING, CHEMICAL | 531182 |
122 | 3 | THERMODYNAMICS//INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER//MECHANICS | 68088 |
756 | 2 | FLOW BOILING//POOL BOILING//CRITICAL HEAT FLUX | 12400 |
7884 | 1 | FUEL COOLANT INTERACTION//SEVERE ACCIDENT//NUCL POWER SAFETY | 1317 |
Terms with highest relevance score |
rank | Term | termType | Chi square | Shr. of publ. in class containing term |
Class's shr. of term's tot. occurrences |
#P with term in class |
---|---|---|---|---|---|---|
1 | FUEL COOLANT INTERACTION | authKW | 831169 | 3% | 81% | 44 |
2 | SEVERE ACCIDENT | authKW | 705813 | 7% | 31% | 97 |
3 | NUCL POWER SAFETY | address | 685841 | 4% | 53% | 56 |
4 | VAPOR EXPLOSION | authKW | 608714 | 2% | 82% | 32 |
5 | CORIUM | authKW | 566738 | 3% | 66% | 37 |
6 | IN VESSEL RETENTION | authKW | 552084 | 2% | 74% | 32 |
7 | NUCLEAR ENGINEERING AND DESIGN | journal | 370367 | 29% | 4% | 385 |
8 | FCI | authKW | 208637 | 1% | 50% | 18 |
9 | CORE CATCHER | authKW | 187788 | 1% | 90% | 9 |
10 | EXTERNAL REACTOR VESSEL COOLING | authKW | 187788 | 1% | 90% | 9 |
Web of Science journal categories |
Rank | Term | Chi square | Shr. of publ. in class containing term |
Class's shr. of term's tot. occurrences |
#P with term in class |
---|---|---|---|---|---|
1 | Nuclear Science & Technology | 65828 | 65% | 0% | 857 |
2 | Thermodynamics | 5030 | 16% | 0% | 214 |
3 | Engineering, Mechanical | 3101 | 16% | 0% | 214 |
4 | Mechanics | 1426 | 12% | 0% | 161 |
5 | Materials Science, Ceramics | 33 | 1% | 0% | 18 |
6 | Engineering, General | 25 | 2% | 0% | 21 |
7 | Physics, Fluids & Plasmas | 20 | 2% | 0% | 20 |
8 | METALLURGY & MINING | 18 | 0% | 0% | 2 |
9 | Engineering, Chemical | 7 | 3% | 0% | 33 |
10 | Physics, Applied | 3 | 4% | 0% | 59 |
Address terms |
Rank | Term | Chi square | Shr. of publ. in class containing term |
Class's shr. of term's tot. occurrences |
#P with term in class |
---|---|---|---|---|---|
1 | NUCL POWER SAFETY | 685841 | 4% | 53% | 56 |
2 | SEVERE ACCIDENT PROJECT | 162287 | 1% | 100% | 7 |
3 | ADV SIMULAT SYST | 103269 | 1% | 64% | 7 |
4 | RISK STUDIES SAFETY | 90861 | 1% | 28% | 14 |
5 | SE2T | 81137 | 1% | 50% | 7 |
6 | ALEKSANDROV TECHNOL | 74187 | 0% | 80% | 4 |
7 | EUROPA KOMMISS | 69552 | 0% | 100% | 3 |
8 | SEVERE ACCID | 64395 | 0% | 56% | 5 |
9 | SEVERE ACCID PHWR SAFETY | 62584 | 1% | 30% | 9 |
10 | NITI | 61821 | 0% | 67% | 4 |
Journals |
Rank | Term | Chi square | Shr. of publ. in class containing term |
Class's shr. of term's tot. occurrences |
#P with term in class |
---|---|---|---|---|---|
1 | NUCLEAR ENGINEERING AND DESIGN | 370367 | 29% | 4% | 385 |
2 | NUCLEAR TECHNOLOGY | 66882 | 9% | 3% | 114 |
3 | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 30610 | 6% | 2% | 82 |
4 | NUCLEAR SAFETY | 19610 | 1% | 4% | 19 |
5 | ANNALS OF NUCLEAR ENERGY | 18062 | 5% | 1% | 67 |
6 | NUCLEAR SCIENCE AND ENGINEERING | 12666 | 3% | 1% | 43 |
7 | HIGH TEMPERATURE | 11078 | 3% | 1% | 43 |
8 | PROGRESS IN NUCLEAR ENERGY | 9471 | 2% | 1% | 32 |
9 | NUCLEAR ENGINEERING AND TECHNOLOGY | 9081 | 1% | 2% | 18 |
10 | JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME | 7663 | 3% | 1% | 46 |
Author Key Words |
Rank | Term | Chi square | Shr. of publ. in class containing term |
Class's shr. of term's tot. occurrences |
#P with term in class |
LCSH search | Wikipedia search |
---|---|---|---|---|---|---|---|
1 | FUEL COOLANT INTERACTION | 831169 | 3% | 81% | 44 | Search FUEL+COOLANT+INTERACTION | Search FUEL+COOLANT+INTERACTION |
2 | SEVERE ACCIDENT | 705813 | 7% | 31% | 97 | Search SEVERE+ACCIDENT | Search SEVERE+ACCIDENT |
3 | VAPOR EXPLOSION | 608714 | 2% | 82% | 32 | Search VAPOR+EXPLOSION | Search VAPOR+EXPLOSION |
4 | CORIUM | 566738 | 3% | 66% | 37 | Search CORIUM | Search CORIUM |
5 | IN VESSEL RETENTION | 552084 | 2% | 74% | 32 | Search IN+VESSEL+RETENTION | Search IN+VESSEL+RETENTION |
6 | FCI | 208637 | 1% | 50% | 18 | Search FCI | Search FCI |
7 | CORE CATCHER | 187788 | 1% | 90% | 9 | Search CORE+CATCHER | Search CORE+CATCHER |
8 | EXTERNAL REACTOR VESSEL COOLING | 187788 | 1% | 90% | 9 | Search EXTERNAL+REACTOR+VESSEL+COOLING | Search EXTERNAL+REACTOR+VESSEL+COOLING |
9 | MCCI | 147636 | 1% | 58% | 11 | Search MCCI | Search MCCI |
10 | MOLTEN CORE | 139103 | 0% | 100% | 6 | Search MOLTEN+CORE | Search MOLTEN+CORE |
Core articles |
The table includes core articles in the class. The following variables is taken into account for the relevance score of an article in a cluster c: (1) Number of references referring to publications in the class. (2) Share of total number of active references referring to publications in the class. (3) Age of the article. New articles get higher score than old articles. (4) Citation rate, normalized to year. |
Rank | Reference | # ref. in cl. |
Shr. of ref. in cl. |
Citations |
---|---|---|---|---|
1 | DOMBROVSKY, LA , (2017) STEAM EXPLOSION IN NUCLEAR REACTORS: DROPLETS OF MOLTEN STEEL VS CORE MELT DROPLETS.INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER. VOL. 107. ISSUE . P. 432 -438 | 44 | 73% | 0 |
2 | ZHANG, LT , ZHOU, YK , ZHANG, YP , TIAN, WX , QIU, SZ , SU, GH , (2015) NATURAL CONVECTION HEAT TRANSFER IN CORIUM POOLS: A REVIEW WORK OF EXPERIMENTAL STUDIES.PROGRESS IN NUCLEAR ENERGY. VOL. 79. ISSUE . P. 167 -181 | 26 | 90% | 2 |
3 | KATAOKA, I , (2013) REVIEW OF THERMAL-HYDRAULIC RESEARCHES IN SEVERE ACCIDENTS IN LIGHT WATER REACTORS.JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY. VOL. 50. ISSUE 1. P. 1 -14 | 35 | 66% | 7 |
4 | MEIGNEN, R , RAVERDY, B , PICCHI, S , LAMOME, J , (2014) THE CHALLENGE OF MODELING FUEL-COOLANT INTERACTION: PART II - STEAM EXPLOSION.NUCLEAR ENGINEERING AND DESIGN. VOL. 280. ISSUE . P. 528 -541 | 22 | 96% | 12 |
5 | MEIGNEN, R , PICCHI, S , LAMOME, J , RAVERDY, B , ESCOBAR, SC , NICAISE, G , (2014) THE CHALLENGE OF MODELING FUEL-COOLANT INTERACTION: PART I - PREMIXING.NUCLEAR ENGINEERING AND DESIGN. VOL. 280. ISSUE . P. 511 -527 | 24 | 83% | 12 |
6 | STARFLINGER, J , BUCK, M , HARTMANN, A , KULENOVIC, R , LEININGER, S , RAHMAN, S , RASHID, M , (2015) RECENT NUMERICAL SIMULATIONS AND EXPERIMENTS ON COOLABILITY OF DEBRIS BEDS DURING SEVERE ACCIDENTS OF LIGHT WATER REACTORS.NUCLEAR ENGINEERING AND DESIGN. VOL. 294. ISSUE . P. 153 -160 | 20 | 100% | 1 |
7 | CHIKHI, N , COINDREAU, O , LI, LX , MA, WM , TAIVASSALO, V , TAKASUO, E , LEININGER, S , KULENOVIC, R , LAURIEN, E , (2014) EVALUATION OF AN EFFECTIVE DIAMETER TO STUDY QUENCHING AND DRY-OUT OF COMPLEX DEBRIS BED.ANNALS OF NUCLEAR ENERGY. VOL. 74. ISSUE . P. 24 -41 | 23 | 85% | 3 |
8 | MORIYAMA, K , PARK, HS , HWANG, B , JUNG, WH , (2016) ANALYSIS OF EX-VESSEL MELT JET BREAKUP AND COOLABILITY. PART 1: SENSITIVITY ON MODEL PARAMETERS AND ACCIDENT CONDITIONS.NUCLEAR ENGINEERING AND DESIGN. VOL. 302. ISSUE . P. 107 -117 | 18 | 100% | 0 |
9 | URSIC, M , LESKOVAR, M , MEIGNEN, R , (2015) EULERIAN MODELLING OF MELT SOLIDIFICATION IMPACT DURING FUEL-COOLANT INTERACTION.ANNALS OF NUCLEAR ENERGY. VOL. 78. ISSUE . P. 130 -139 | 18 | 100% | 0 |
10 | REMPE, JL , SUH, KY , CHEUNG, FB , KIM, SB , (2008) IN-VESSEL RETENTION OF MOLTEN CORIUM: LESSONS LEARNED AND OUTSTANDING ISSUES.NUCLEAR TECHNOLOGY. VOL. 161. ISSUE 3. P. 210-267 | 38 | 49% | 31 |
Classes with closest relation at Level 1 |