Critical experiment on initial loading core of very high temperature reactor critical assembly (VHTRC)
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
A critical assembly VHTRC (Very High Temperature Reactor Critical Assembly) was constructed by modifying SHE (Semi-Homogeneous Experiment) in order to verify the nuclear design accuracy of the HTTR (High Temperature Engineering Test Reactor). The initial core named as VHTRC-1 core was made by loading fuel rods which contained fuel compacts of 4 W/0 enriched uranium coated particles. The following measurements were carried out in the VHTRC-1 core: (1) critical mass, (2) reactivity worths of mockup control rod and burnable poison rod, (3) neutron flux distribution and (4) kinetic parameter βeff/Λ. Calculations were performed with the SRAC code system using the nuclear data based on the ENDF/B-IV. The agreement between experiment and calculation was fairly good for the most experimental items. The calculation, however, cannot predict accurately the value of the kinetic parameter. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.31.682Abstract (Japanese)
高温ガス炉の核的安全性実証のための主要な臨界試験項目は以下の通りであり、当面は高温工学試験研究炉(High Temperature Engineering Test Reactor; HTTR)の初期炉心が対象となるが、その実験終了後は高度化炉心について研究を進める予定である。(1)反応度バランス核設計上の課題となっている制御棒・可燃性毒物の反応度価値について模擬炉心実験を行い、炉停止余裕や運転余裕に関して実験的検証を行う。(2)出力分布HTTRは炉心温度が高いことおよびブロック構造のため、出力運転中に炉心内の出力および温度の空間分布を実測することが困難である。このため核計算で求めた核分裂密度を熱源とする伝熱流動計算によって出力および温度の空間分布を推定し、運転をして行くことになる。したがって、予め臨界実験によって3次元的な出力分布の計算精度を検証しておく必要がある。(3)核特性の温度依存性炉心を昇温して反応度温度係数の測定を行うほか、炉心温度による炉心核特性の変化の予測精度を確認する。本報は、初回臨界炉心VHTRC-1炉心における臨界質量、制御棒、可燃性毒物棒模擬体の反応度価値、中性子束分布等の実験結果について述べる。(日本)Additional details
Additional titles
- Original title (Japanese)
- 高温ガス炉臨界実験装置(VHTRC)の初装荷炉心における臨界実験
Identifiers
- DOI
- 10.3327/jaesj.31.682;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 31
- Journal Issue
- 6
- Journal Page Range
- p. 682-690
- ISSN
- 0004-7120
- CODEN
- NGEGAL
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54004161
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNABLE POISONS; CONTROL ELEMENTS; CRITICALITY; EXPERIMENTAL REACTORS; HTTR REACTOR; ISOTOPE RATIO; NEUTRON FLUX; POWER DISTRIBUTION; REACTIVITY; REACTIVITY WORTHS; REACTOR CORES; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 1000-4000 K; ZERO POWER REACTORS
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; NEUTRON ABSORBERS; NUCLEAR POISONS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE
Optional Information
- Notes
- This record replaces 21032217