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Effective Cross Section Values for Well-Moderated Thermal Reactor Spectra: 3rd edition corrected. (CRRP-960), (EANDC(Can)-4), (TNCC(Can)-30) AECL-1101

Effective Cross Section Values for Well-Moderated Thermal Reactor Spectra: 3rd edition corrected. (CRRP-960), (EANDC(Can)-4), (TNCC(Can)-30) AECL-1101
Paper規格・テクニカルリポート類
Westcott, C. H1960<M-AECL-1101>
National Diet Library

COMPILATION OF THRESHOLD REACTION NEUTRON CROSS SECTIONS FOR NEUTRON DOSIMETRY AND OTHER APPLICATIONS. (EANDC ; EANDC-95-U)

COMPILATION OF THRESHOLD REACTION NEUTRON CROSS SECTIONS FOR NEUTRON DOSIMETRY AND OTHER APPLICATIONS. (EANDC ; EANDC-95-U)
Paper図書
SCHETT, A.(et al.)1974.
Other Libraries in Japan

AVERAGE NUMBER OF EMITTED NEUTRONS IN FISSION. (EANDC ; EANDC-E-154-U)

AVERAGE NUMBER OF EMITTED NEUTRONS IN FISSION. (EANDC ; EANDC-E-154-U)
Paper図書
RIBON, P.(ed.)1973.
Other Libraries in Japan

The total neutron cross section of Fe54 in the keV energy region (EANDC(E) ; EANDC(E)-145-U)

The total neutron cross section of Fe54 in the keV energy region (EANDC(E) ; EANDC(E)-145-U)
Paper図書
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Angewandte Kernphysik; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter(Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Angewandte Kernphysik; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter)1972.
Other Libraries in Japan

REVIEW OF THE TOTAL RADIATION WIDTHS OF THE NEUTRON RESONANCES OF U-238. (EANDC ; EANDC-US-179-U)

REVIEW OF THE TOTAL RADIATION WIDTHS OF THE NEUTRON RESONANCES OF U-238. (EANDC ; EANDC-US-179-U)
Paper図書
RAHN, F.(et al.)1972.
Other Libraries in Japan

Neutron cross sections. Volume II. Curves (BNL ; BNL-325(Ed.3)(Vol.2); EANDC(US)-183; INDC(USA)-58)

Neutron cross sections. Volume II. Curves (BNL ; BNL-325(Ed.3)(Vol.2); EANDC(US)-183; INDC(USA)-58)
Paper図書
Garber, D.I., Kinsey, R.R.Brookhaven National Lab.1976.1.
Other Libraries in Japan

Status of the Karlsruhe evaluated nuclear data file KEDAK at June 1970 (EANDC(E) ; EANDC(E)-136-U)

Status of the Karlsruhe evaluated nuclear data file KEDAK at June 1970 (EANDC(E) ; EANDC(E)-136-U)
Paper図書
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik(Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik)1971.
Other Libraries in Japan

Evaluation of fast critical experiments using recent methods and data (EANDC(E) ; EANDC(E)-118-U)

Evaluation of fast critical experiments using recent methods and data (EANDC(E) ; EANDC(E)-118-U)
Paper図書
Kernforschungszentrum Karslruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik(Kernforschungszentrum Karslruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik)1970.
Other Libraries in Japan

PROGRESS REPORT TO EANDC FROM AUSTRIA (SGAE ; SGAE-PH-126-72)

PROGRESS REPORT TO EANDC FROM AUSTRIA (SGAE ; SGAE-PH-126-72)
Paper図書
EDER,O.J.1972.
Other Libraries in Japan

Proceedings of the EANDC topical discussion on Critique of Nuclear Models and Their Validity in the Evaluation of Nuclear Data (JAERI-M ; JAERI-M-5984)

Proceedings of the EANDC topical discussion on Critique of Nuclear Models and Their Validity in the Evaluation of Nuclear Data (JAERI-M ; JAERI-M-5984)
Paper図書
Fuketa Toyojiro日本原子力研究所1975.
Other Libraries in Japan

The total neutron cross sections of 50Cr, 52Cr, 62Ni and 64Ni in the energy region 10-300 keV (EANDC(E) ; EANDC(E)-146-U)

The total neutron cross sections of 50Cr, 52Cr, 62Ni and 64Ni in the energy region 10-300 keV (EANDC(E) ; EANDC(E)-146-U)
Paper図書
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Angewandte Kernphysik; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter(Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Angewandte Kernphysik; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter)1972.
Other Libraries in Japan

Neutron cross sections. Volume I. Resonance parameters (BNL ; BNL-325(3rd Ed.)(Vol.1)) (EANDC ; EANDC(US)-183(L)) (INDC ; INDC(USA)-58(L))

Neutron cross sections. Volume I. Resonance parameters (BNL ; BNL-325(3rd Ed.)(Vol.1)) (EANDC ; EANDC(US)-183(L)) (INDC ; INDC(USA)-58(L))
Paper図書
S.F. Mughabghab, D.I. Garber1973
Other Libraries in Japan

JAPANESE PROGRESS REPORT TO THE EANDC. (JAERI-レポート ; JAERI-13305)

JAPANESE PROGRESS REPORT TO THE EANDC. (JAERI-レポート ; JAERI-13305)
Paper図書
MOMOTA, T.(et al.)日本原子力研究所(ニホン ゲンシリョク ケンキュウショ)1968.
Other Libraries in Japan

「核データの評価における核模型とその妥当性の評論」に関するEANDC トピカル・ディスカッション報告

「核データの評価における核模型とその妥当性の評論」に関するEANDC トピカル・ディスカッション報告
Digital文書・図像類
更田 豊治郎1975-02JAERI-M 5984
Other Libraries in Japan
  • Summary, etc.日本で行われた欧米核データ委員会(EANDC、現在 NEA核データ委員会、NEANDCと改名)第17回会合にあわせて、1974年3月27日に行われ...
  • Note (General)日本で行われた欧米核データ委員会(EANDC、現在 NEA核データ委員会、NEANDCと改名)第17回会合にあわせて、1974年3月27日に行われ...
  • Alternative TitleProceedings of the EANDC topical discussion on Critiqu...

STATUS OF MEASUREMENTS OF THE TOTAL CROSS SECTION OF PA-233. (EANDC ; EANDC-US-44-L)

STATUS OF MEASUREMENTS OF THE TOTAL CROSS SECTION OF PA-233. (EANDC ; EANDC-US-44-L)
Paper図書
BURGUS, W.H.(et al.)1963.
Other Libraries in Japan

MICROSCOPIC NEUTRON NUCLEAR DATA AND 5-GROUP CROSS SECTIONS FOR THE ACTINIDES 231PA, 232U, 234U, 236U, 237U, 237NP, 238NP, 236PU, 238PU, 241AM, 242CM. (KFK ; KFK-1186; EANDC(E)-128-U)

MICROSCOPIC NEUTRON NUCLEAR DATA AND 5-GROUP CROSS SECTIONS FOR THE ACTINIDES 231PA, 232U, 234U, 236U, 237U, 237NP, 238NP, 236PU, 238PU, 241AM, 242CM. (KFK ; KFK-1186; EANDC(E)-128-U)
Paper図書
HINKELMANN, B.1970.
Other Libraries in Japan

NEUTRON CROSS SECTIONS: ANGULAR DISTRIBUTIONS (EANDC(US) ; EANDC(US)-138-U)

NEUTRON CROSS SECTIONS: ANGULAR DISTRIBUTIONS (EANDC(US) ; EANDC(US)-138-U)
Paper図書
1956.
Other Libraries in Japan

HIGH-RESOLUTION NEUTRON SPECTROSCOPY IN THE KEV REGION: AL, TI, FE, NI, CU, ZN, V, MN, CO AND BI. (TID ; TID-21144; EANDC(US)-54(L); CR-1860)

HIGH-RESOLUTION NEUTRON SPECTROSCOPY IN THE KEV REGION: AL, TI, FE, NI, CU, ZN, V, MN, CO AND BI. (TID ; TID-21144; EANDC(US)-54(L); CR-1860)
Paper図書
GARG, J.B.(et al.)1964.
Other Libraries in Japan

Effective cross section values for well-moderated thermal reactor spectra. (3rd edition corrected) (AECL ; AECL-1101) (CRRP ; CRRP-960) (EANDC(Can) ; EANDC(Can)-4) (TNCC(Can) ; TNCC(Can)-30)

Effective cross section values for well-moderated thermal reactor spectra. (3rd edition corrected) (AECL ; AECL-1101) (CRRP ; CRRP-960) (EANDC(Can) ; EANDC(Can)-4) (TNCC(Can) ; TNCC(Can)-30)
Paper図書
C.H. Westcott1960
Other Libraries in Japan

JAERI-M 1555,2704,2961

JAERI-M 1555,2704,2961
PaperDigital図書障害者向け資料あり
日本原子力研究所 [編]日本原子力研究所1964.4-1969.6<NG31-13>
Available onlineNational Diet Library
  • Contents... Report to the EANDC(January to December,1967 incl...
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