SCOPUS 정보 검색 플랫폼

Volumn 77, Issue 10, 2000, Pages 575-584

Re-embrittlement behaviour of VVER-440 reactor pressure vessel weld material after annealing

Author keywords

Re embrittlement behaviour; Thermal annealing treatment; Weld materials

Indexed keywords

ANNEALING; CHROMIUM ALLOYS; EMBRITTLEMENT; FRACTURE TOUGHNESS; IMPACT TESTING; PRECIPITATION (CHEMICAL); WELDS;

POST-IRRADIATION THERMAL ANNEALING; REACTOR PRESSURE VESSELS (RPV);

PRESSURE VESSELS;

ANNEALING; EMBRITTLEMENT; IRRADIATION; PRESSURE VESSEL; WELD METAL;

EID: 0034240795 PISSN: 03080161 EISSN: None Source Type: Journal
DOI: 10.1016/S0308-0161(00)00029-6 Document Type: Article

Times cited : (24)

References (10)

2
- 85001799716
- The actual properties of WWER-440 reactor pressure vessel materials obtained by impact tests of subsize specimens fabricated out of samples taken from RPV
- In: Corwin WR, Rosinski ST, van Walle E, editors; ASTM STP 1329 Philadelphia: American Society for Testing and Materials
- (1997) Small Specimen Test Techniques
- Korolev, Y.¹ Kryukov, A.² Langer, R.³ Leitz, C.⁴ Nikolaev, V.⁵ Nikolaev, Y.⁶ Platonov, P.⁷ Reig, C.⁸ Shtrombach, Y.⁹

3
- 0027187166
- Radiation stability of WWER-440 vessel materials
- In: Steele LE, editor; Philadelphia, PA: American Society for Testing and Materials
- (1993) Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review, ASTM STP 1170 , pp. 9-29
- Amayev, A.¹ Kryukov, A.² Levit, V.³ Sokolov, M.⁴

4
- 0032309779
- Effects of post-irradiation thermal annealing on radiation embrittlement behaviour of Cr-Mo-V alloyed weld metals
- published by the Finnish Academy of Technology, Espoo; ISBN, ISSN
- (1998) Acta Polytechnica Scandinavica, Mechanical Engineering Series No. , pp. 112
- Kohopaa, J.¹

5
- 0027205754
- Recovery of the transition temperature of irradiated WWER-440 vessel metal by annealing
- In: Steele LE, editor; Philadelphia, PA: American Society for Testing and Materials
- (1993) Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review, ASTM STP 1170 , vol.4 , pp. 369-379
- Amayev, A.¹ Kryukov, A.² Sokolov, M.³

6
- 0006724506
- Annealing results from surveillance programmes of WWER-440 reactor pressure vessel materials
- IWG-LMNPP-95/5, International Atomic Energy Agency, Vienna
- (1995) IAEA Specialist Meeting on Irradiation Embrittlement and Mitigation, October 23-26 1995, Espoo, Finland
- Brumovsky, M.¹ Kytka, M.² Novosad, P.³

7
- 0006648956
- Annealing behaviour of Loviisa-1 surveillance materials measured with V-notched specimens and the current status of vessel anneal
- US Nuclear Regulatory Commission, Washington DC
- (1997) Twenty-Fourth Water Reactor Safety Information Meeting, 21 - 23 October, 1996, Bethesda, MD, NUREG/CP-0157 , vol.2 , pp. 81-97
- Valo, M.¹ Kohopaa, J.² Wallin, K.³ Planman, T.⁴

8
- 0023142916
- A model for PWR pressure vessel embrittlement
- (1987) Int J Pres Ves Piping , vol.27 , pp. 91-135
- Fisher, S.¹ Buswell, J.²

9
- 0027151075
- Surveillance of WWER-440C reactor pressure vessels
- In: Steele LE, editor; Philadelphia, PA: American Society for Testing and Materials
- (1993) Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review, ASTM STP 1170 , vol.4 , pp. 57-70
- Brumovsky, M.¹ Pav, T.²

10
- 0027289831
- Analysis of the surveillance results at paks nuclear power plant
- In: Steele LE, editor; Philadelphia, PA: American Society for Testing and Materials
- (1993) Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review, ASTM STP 1170 , vol.4 , pp. 49-56
- Oszvald, F.¹ Trampus, P.²

* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.