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International Journal of Pressure Vessels and Piping

Volumn 77, Issue 10, 2000, Pages 585-590

Examination of VVER-440 RPV steel re-irradiation behavior using materials from operating units

(1) Shtrombakh, Ya I a

a KURCHATOV INSTITUTE (Russian Federation)

Author keywords

Ductile to brittle transition temperature; Impact bend specimens; RPV steel

Indexed keywords

DEGRADATION; DUCTILITY; EMBRITTLEMENT; NUCLEAR POWER PLANTS; STEEL STRUCTURES; THERMOANALYSIS;

DUCTILE-TO-BRITTLE TRANSITION TEMPERATURE (DBTT); REACTOR PRESSURE VESSELS (RPV);

PRESSURE VESSELS;

DUCTILE-BRITTLE TRANSITION; IRRADIATION; PRESSURE VESSEL; STEEL;

EID: 0034240802 PISSN: 03080161 EISSN: None Source Type: Journal
DOI: 10.1016/S0308-0161(00)00030-2 Document Type: Article

Times cited : (4)

References (7)

1
- 0006689208
- Irradiation damage of water-water reactor vessel steels
- Moscow, Russia: Energoizdat
- (1981) , pp. 191
- Alexeyenko, I.N.¹ Amaev, A.D.² Gorynin, I.V.³ Nikolaev, V.A.⁴

2
- 0031210068
- Assessment of relative contributions from different mechanisms to radiation embrittlement of reactor pressure vessel steels
- (1997) J Nucl Mater , vol.246 , pp. 91-120
- Gurovich, B.A.¹ Kuleshova, E.A.² Shtrombakh, Yu.A.³ Nikolaev, Ya.I.⁴

3
- 0006691637
- Examination of the materials from operating VVER pressure vessels
- (1998) Proceedings of the International Symposium Fontevaurd IV , vol.1 , pp. 45-60
- Shtrombakh, Ya.I.¹ Kryukov, A.M.² Platonov, P.A.³ Langer, R.⁴ Rieg, C.-Y.⁵

4
- 0006654151
- Verification of the scheme applied for evaluation of radiation embrittlement proceeding in VVER-440 pressure vessel materials
- (1998) Proceedings of the International Symposium Fontevaurd IV , vol.1 , pp. 37-43
- Kryukov, A.M.¹ Nikolaev, Yu.A.² Platonov, P.A.³ Shtrombakh, Ya.I.⁴

5
- 0002536702
- Investigation of samples taken from Kozloduy unit 2 reactor pressure vessel
- (1996) Nuclear Engineering and Design , vol.160 , pp. 59-76
- Kryukov, A.¹ Platonov, P.² Shtrombakh, Ya.³ Nikolaev, V.⁴ Klausnitzer, E.⁵ Leitz, C.⁶ Rieg, C.-Y.⁷

6
- 0000737734
- Learning from investigation programmes on WWER 440/230 RPVs
- (1996) Proceedings of Fourth International Conference on Material Science Problems in NPP Equipment , vol.1 , pp. 165-181
- Leitz, C.¹ Langer, R.² Platonov, P.³ Shtrombakh, Ya.I.⁴ Kryukov, A.⁵ Rybin, V.⁶ Nikolaev, V.⁷ Rieg, C.-Y.⁸

7
- 0032230750
- The actual properties of WWER-440 reactor pressure vessel materials obtained by impact tests of subsize specimens fabricated out of samples taken from the RPV
- In: Corwin WR, Rosinski ST, van Walle E, editors
- Small Specimen Test Techniques, ASTM STP 13291998 , pp. 145-159
- Korolev, Yu.N.¹ Kryukov, A.M.² Nikolaev, Yu.A.³ Platonov, P.A.⁴ Shtrombakh, Ya.I.⁵ Langer, R.⁶ Leitz, C.⁷ Rieg, C.-Y.⁸

* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.