COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems ; Equations and Constitutive Models (NUREG ; NUREG/CR-3046-VOL.1; PNL-4385-VOL.1)

COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems ; Equations and Constitutive Models

(NUREG ; NUREG/CR-3046-VOL.1; PNL-4385-VOL.1)

Material type: 図書

Author: Thurgood, M.J./Kelly, J.M./and others

Publisher: NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))

Publication date: 1983.

Material Format: Paper

Capacity, size, etc.: 1 VOL

NDC: -

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Paper

Material Type: 図書
Title: COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems ; Equations and Constitutive Models
Author/Editor: Thurgood, M.J./Kelly, J.M./and others
Series Title: NUREG ; NUREG/CR-3046-VOL.1; PNL-4385-VOL.1
Author Heading: Thurgood, M.J.
Kelly, J.M.
and others
Publication, Distribution, etc.: NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))
Publication Date: 1983.
Publication Date (W3CDTF): 1983
Extent: 1 VOL
Place of Publication (Country Code): us
Text Language Code: eng
Target Audience: 一般
Data Provider (Database): 日本原子力研究開発機構 : 日本原子力研究開発機構所蔵目録データベース
https://library-documents.jaea.go.jp/opac/opac_search/