Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part III CANDU-Type fuel with H2O-D2O mixtures as coolants. (CRRP-985-C) AECL-1419

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part III CANDU-Type fuel with H2O-D2O mixtures as coolants. (CRRP-985-C)

AECL-1419

Call No. (NDL): M-AECL-1419
Bibliographic ID of National Diet Library: 000005873284

Material type: 規格・テクニカルリポート類

Author: Chidley, B. Gほか

Publisher: -

Publication date: 1961

Material Format: Paper

Capacity, size, etc.: 101 p

NDC: -

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Paper

Material Type: 規格・テクニカルリポート類
Title: Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part III CANDU-Type fuel with H2O-D2O mixtures as coolants. (CRRP-985-C)
Author/Editor: Chidley, B. G
Turner, R. B
Bigham, C. B
Publication Date: 1961
Publication Date (W3CDTF): 1961
Extent: 101 p
Report No.: テクニカルリポート番号 : AECL-1419
Holding library: 国立国会図書館
Call No.: M-AECL-1419
Data Provider (Database): 国立国会図書館 : 国立国会図書館蔵書
https://ndlsearch.ndl.go.jp
Bibliographic ID (NDL): 000005873284
http://id.ndl.go.jp/bib/000005873284
Bibliographic Record Category (NDL): 291