Published 2017 | Version v1
Miscellaneous Metadata-only

Relationship between damaging capacity of virtual vessel reactor steel and neutron flux intensity

Creators

  • 1. Natsional'nyj Issledovatel'skij Tsentr «Kurchatovskij Inst.», Moscow (Russian Federation)

Description

no abstract available

Part of:
The Twelfth International Ural Seminar Radiation damage physics of metals and alloys. Abstracts

Additional details

Additional titles

Original title (Russian)
Зависимост' повреждаемости виртуальной корпусной реакторной стали от интенсивности нейтронного потока

Publishing Information

Publisher
IFM UrO RAN
Imprint Place
Ekaterinburg (Russian Federation)
Imprint Title
The Twelfth International Ural Seminar Radiation damage physics of metals and alloys. Abstracts
Imprint Pagination
109 p.
Journal Page Range
p. 37-38
Report number
INIS-RU--609

Conference

Title
12. International Ural Seminar Radiation damage physics of metals and alloys
Original Conference Title
Dvenadtsatyj Mezhdunarodnyj Ural'skij Seminar Radiatsionnaya fizika metallov i splavov
Dates
27 Feb - 4 Mar 2017
Place
Kyshtym (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
49102144
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
No Abstract, Conference
Descriptors DEI
EMBRITTLEMENT; FAST NEUTRONS; NEUTRON FLUX; RADIANT FLUX DENSITY; REACTOR VESSELS; STAINLESS STEELS; WWER TYPE REACTORS
Descriptors DEC
ALLOYS; BARYONS; CARBON ADDITIONS; CONTAINERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; FLUX DENSITY; HADRONS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; NEUTRONS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs. Imprint:Dvenadtsatyj Mezhdunarodnyj Ural'skij Seminar Radiatsionnaya fizika metallov i splavov. Tezisy dokladov