REACTOR-RA FUEL BURNUP MEASUREMENT BY SPATIAL POWER DISTRIBUTION AND THE GAMMA-SPECTROMETRY METHOD.

被引：0

作者：

Martinc, R.

Bulovic, V.

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Polymer Bulletin (Berlin) | 1978年 / 1卷

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引用

页码：339 / 351

共 39 条

[1] Method for the determination of neutron field monitor burnup effects by gamma-spectrometry
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Simonits, AP
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ANALYTICAL COMMUNICATIONS, 1997, 34 (05): : 133 - 135
[2] GAMMA-SPECTROMETRY, MEASUREMENT METHOD IN HEALTH PHYSICS
VOICU, V
STUDII SI CERCETARI DE FIZICA, 1970, 22 (04): : 437 - +
[3] STUDY OF MIGRATION OF FISSION FRAGMENTS IN FUEL-ELEMENTS, BY GAMMA-SPECTROMETRY METHOD
SUKHIKH, AV
DAVYDOV, EF
SOVIET ATOMIC ENERGY-USSR, 1971, 30 (02): : 292 - &
[4] GAMMA-SPECTROMETRY AND METALLOGRAPHY OF FUEL-ELEMENTS IN WORKING CASSETTE OF IVV-2 REACTOR
BYCHENKOV, VV
ZELENO, VI
KARPECHKO, SG
PANKOV, EN
TIMOKHIN, AN
SOVIET ATOMIC ENERGY, 1975, 38 (05): : 383 - 387
[5] THE OPTIMUM FUEL AND POWER DISTRIBUTION FOR A PRESSURIZED WATER-REACTOR BURNUP CYCLE
STILLMAN, JA
CHAO, YA
DOWNAR, TJ
NUCLEAR SCIENCE AND ENGINEERING, 1989, 103 (04) : 321 - 333
[6] MEASUREMENT OF RATIO OF CAPTURE TO FISSION IN 238U BY GAMMA-SPECTROMETRY METHOD
YUROVA, LN
BUSHUEV, AV
JOURNAL OF NUCLEAR ENERGY, 1967, 21 (01): : 106 - &
[7] DETERMINATION OF SOME CHARACTERISTICS OF SPENT FUEL OF BOILING-WATER REACTOR USING ALPHA-SPECTROMETRY AND GAMMA-SPECTROMETRY
ZELENKOV, AG
PIROZHKOV, SV
RODIONOV, YF
SHVETSOV, IK
SOVIET ATOMIC ENERGY, 1980, 49 (02): : 520 - 524
[8] A simple gamma spectrometry method for evaluating the burnup of MTR-type HEU fuel elements
Makmal, T.
Aviv, O.
Gilad, E.
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2016, 834 : 175 - 182
[9] FUEL ROD SCANNER FOR REACTOR POWER DENSITY DISTRIBUTION MEASUREMENT
KOBAYASH.S
MATSUOKA, K
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-TOKYO, 1965, 2 (12): : 485 - +
[10] CALCULATION OF FUEL-CYCLE BURNUP AND POWER DISTRIBUTION OF DRESDEN-1 REACTOR WITH TRILUX FUEL MANAGEMENT PROGRAM
GOLDSTEIN, L
NAKACHE, F
VERAS, A
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (01): : 300 - +

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